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  • Progress of China Experimental Fast Reactor in 2011
  • 1 Background Fast reactor is the reactor which realized the chain fission with fast neutron.As an optional type of generation Ⅳ reactor,fast reactor has three characters:1) It can change 238U to 239Pu and raise the uranium resource utilization
  • Progress of Project “The Key Technology Research of Passive Shutdown System for CDFR”
  • Passive shutdown technology is one of the key technologies to increase safety performance of larger-size sodium-cooled fast reactors. The objective to the project was to develop the preliminary design of the rod on the basis of theoretic analysis of passive shutdown assembly.
  • Summary of Research on Interactive Safety Analysis Program of Pool Type SFR
  • The aim of the project was to develop an interactive safety analysis program of pool type sodium cooled fast reactors (SFR), based on a French system code OASIS. The function and physical model of the program should be verified by the application on CEFR design.
  • PREFACE
  • In the past year of 2011,according to the directions of related governmental departments,under the direct leadership of China National Nuclear Corporation(CNNC) and in the spirit of the annual work conference,China Institute of Atomic Energy
  • Application of INPRO Methodology in Evaluation of Nonproliferation Features of TWR
  • Through the once-through fuel cycle mode, the Traveling Wave Reactor (TWR) concept can utilize the uranium resources much effectively. The once-through fuel cycle has the inherent characteristics of the non-proliferation. In this project,
  • Measurement and Analysis of Sodium Void Reactivity Effect in CEFR
  • The sodium void reactivity effect (SVRE) is one of the important parameters in the design and safety analysis of sodium-cooled fast reactors. In some serious accident conditions, for example the total instantaneous blockage (TIB) accident,
  • Thermal Fatigue Analysis of Takeover Pipeline
  • This article uses the finite element analysis software ANSYS to analyze the fatigue life of the three links pipeline with different angles in the first level pipe of experimental fast reactor. The fatigue analysis is operated following the startup and shutdown process which has two load step,
  • Analysis of Design of Sodium Reception and Secondary Loop Sodium Plugging and Removal System for Fast Reactor
  • Through comparison of sodium reception and secondary loop sodium plugging and removal system on CEFR with BN-800, the main difference of the two designs is as follows: 1) System division is different. BN-800 can be divided into sodium reception system,
  • coustic Leak Detection Based on Wavelet Packet and Genetic Algorithm for LM FBR Steam Generators
  • Steam generator is one kind of key equipments in liquid metal fast breeder reactors (LM FBR) whose reliability will influence the safety of nuclear power plant. We can see that SG is the highest risky equipment from the running experience
  • Research on Valve Body Design of Large Bore Sodium Valve
  • Large bore sodium valve is one kind of key equipments of China Demonstration Fast Reactor (CDFR). It is installed in the pipeline before and behind SG units as a locking mechanism. Valve body which is used to bear pressure is the core of sodium valve design.
  • Analysis of Leak Before Break and Calculation Method of Critical Crack
  • Now leak before break (LBB) technology is widely used in nuclear power plant design. It has a good development in foreign countries, but domestic research is relatively little. The study of crack propagation is core of LBB analysis. It
  • Manufacture of Simulator of Irradiation Device for China Experimental Fast Reactor
  • This research belongs to the development of nuclear energy project of CEFR irradiation device design and previous studies of cladding material 316 (Ti) SS irradiation performance. The main content of the research is the development of irradiation
  • Progress of Research on Demonstration Fast Reactor Main Pipe Material
  • The main characteristics of the sodium pipe system in demonstration fast reactor are high-temperature, thin-wall and big-caliber, which is different from the high-pressure and thick-wall of the pressurized water reactor system, and the system is long-term
  • China Advanced Research Reactor Project Progress in 2011
  • 2011, China Advanced Research Reactor (CARR) Project finished the B stage commissioning and resolved the relative technical problems. Meanwhile, the acceptance items and the cold neutron source were carrying out.
  • Progress Report of Beijing Radioactive Ion-Beam Facility (BRIF) in 2011
  • The year 2011 is featured with several important events for the Beijing Radioactive Ion-beam Facility (BRIF) project. At the beginning of the year, the two divisions of the BRIF project, i.e. Engineering Division and Technology Division, have been merged into one as the BRIF Division.
  • Construction Progress of CYCIAE-100
  • Significant progress has been achieved in 2011 with respect to CYCIAE-100, a key task for the BRIF project. All the work has been fully accomplished in line with the schedule and goals set for the year. 1 General progress for CYCIAE-100
  • Completion of Main Magnet Fabrication for CYCIAE-100
  • The main magnet of CYCIAE-100, which weighs roughly 416 tons after machining, is mainly consisting of 4 pairs of sector magnets, 4 return yokes, top/bottom yoke, central plug, and shimming bars. It falls into the category of large-scale high precision device,
  • Progress of the Water Cooling System for CYCIAE-100
  • The civil building construction of the BRIF project started at the end of April in 2011. The key systems of CYCIAE-100 were completed one after another. The water cooling system for CYCIAE-100 also made a significant progress in 2011, and its progress can be summarized as follows.
  • Main Magnet Installation in the Temporary Building for CYCIAE-100
  • The main magnet of CYCIAE-100 was delivered to CIAE on October 5th, 2011, following which the installation was conducted in the temporary building. The temporary building is located in the south of the cyclotron lab, and the equipments of the
  • Installation and Commissioning of the Main Magnet Elevating System for CYCIAE-100
  • The main magnet elevating system is a key part for CYCIAE-100. The raising device will play an important role throughout the process of installation, magnetic mapping, vacuum leak detection, beam commissioning, and maintenance.
  • Installation of the Magnetic Mapping Device for CYCIAE-100
  • On November 9, 2011, the installation for the main magnet of CYCIAE-100 was completed in the BRIF temporary building, entering into the stage of magnetic mapping and shimming. The mapper has been a specially designed two-dimensional auto-control mapping device,
  • Mapping and Shimming of Magnetic Field in CYCIAE-14
  • The mapping system of magnetic field in CYCIAE-14 is comprised of rotatable beam, stepping motor, optical encoder, Tesla meter, driving system and position system, etc. In order to get the high precision in azimuthal position,
  • Primary Design and Study of the Lattice Structure in Scaling FFAG
  • The principle of FFAG (Fixed Field Alternating Gradient) accelerator, which was first put forward independently by Ohkawa, Symon and Kolomensky in 1950s and then developed rapidly in 1990s, has in recent years become a new direction
  • Processing and Installation of the Stripping Probe for CYCIAE-100
  • The stripping extraction system for CYCIAE-100 is designed to extract proton beams of 75-100 MeV in dual opposite directions by charge exchange stripping devices. The stripping probe is the most critical and complicated device in the system.
  • Mechanic Design of the Radial Probe Target for CYCIAE-100
  • The radial probe target is an important diagnostic component of CYCIAE-100 that adopts blocking measurement. The probe placed in the median plane of sector gap of the cyclotron is mainly used to measure both the radial and vertical cross-sections of the beam,
  • Calculation of New Beam Dump Shielding for CYCIAE-100
  • The 100 MeV high intensity cyclotron, CYCIAE-100, places a demanding requirement on the collection device to accept the proton beam. According to the original design, the beam dump would be settled in the cyclotron vault. It uses pure aluminum as the target material,
  • Development of Pre-amplifier Module for BF_3 Counting Tube
  • According to the calculation of radiation protection, the neutron energy in the cyclotron vault ranges from the thermal neutrons to 100 MeV when the machine is in operation. To monitor the neutron energy on such a wide domain requires special
  • Design and Experimental Study of the External H~- Ion Source for a 10 MeV Medical Cyclotron
  • A 10 MeV medical cyclotron has been designed by the BRIF Division at CIAE, for which the H- beam is axially injected to the machine. To satisfy the requirement for the cyclotron with H- ion source, a compact multicusp H- ion source has
  • Design of a Compact Pulsed Power Accelerator
  • A 100 kA/60 ns compact pulsed power accelerator was designed to study the influence to the X-pinch by the load. It is composed of a Marx generator, a combined pulse forming (PFL), a gas-filled V/N field distortion switch, a transfer line,
  • Design of Spiral Inflector and Central Region for a Medical Cyclotron
  • CYCIAE-14 is a medical cyclotron designed to accelerate H- ions and extract protons, and it adopts the external ion source and axial injection line. The spiral inflector and the central region are the important
  • Design of Main Elements of the Axial Injection Line for CYCIAE-100
  • The 100 MeV high intensity cyclotron CYCIAE-100 uses an external ion source which provides H- beam with an energy up to 40 keV and a maximum current 10 mA. The axial injection system is employed to transport H- beam from the ion
  • Peak Detector Circuit for DCCT Improvement
  • The DCCT(DC Current Transformer)system can be used to measure the DC component or average current intensity (a very important parameter for the cyclotron and beam line) without disturbing the beam for long period. 1 Working principle of DCCT
  • Manufacture of the RF Cavity for CYCIAE-100
  • The RF cavity is a key component for the RF system in CYCIAE-100, the low power consumption and the high stability must be considered in the design to meet the physical needs. It is required that the voltage at the central region is 60 kV
  • Mechanical Design of the Injection Beam Line of Small Medical Cyclotron
  • The injection beam line is a key device for beam transport of the small medical cyclotron, giving direct influence to the beam quality of the cyclotron. According to the medical needs of the cyclotron, the overall length of the injection beam line is as short as possible,
  • Mechanical Design of the Inflector and Central Region of Small Medical Cyclotron
  • The inflector and central region are key devices of the small medical cyclotron, whose structure will give influence to the performance of the cyclotron. According to the needs of the small medical cyclotron, the inflecting voltage of the inflector is ±10 kV.
  • Measurement and Simulation of Beam Centering on CYCIAE-10
  • The beam centering is very important for the compact cyclotron, especially for the cyclotrons with the axial injection. It is critical that the cyclotron has a good beam centering to increase the beam current and reduce the beam loss. In the accelerating process,
  • Simulation on the Pulsed Beam Transport for Injection Line of CYCIAE-10
  • 1 Introduction The development of a 40 keV, 18 mA multi-cusp H- ion source and beam pulsing system have been completed successfully at CIAE. The pulsed H- beam with a repetition rate of 4.4 MHz and a pulse length of 9.6 ns has been obtained. In order to
  • Insulation Consideration of the Cryo-vacuum System for CYCIAE-100
  • A set of tailored cryopanel cooled by a stirling cryogenerator is being developed for the vacuum system of CYCIAE-100. A 25m long transfer line is used to transport cold powder generated by stirling cryogenerator to the tailored cryopanel.
  • Concept Design of Multipacting Measurement Circuit With Nano-second Resolution
  • Multipacting is the phenomena that an electron exerts impact on one surface or between several surfaces of the RF or microwave components under the influence of periodical electric field, and emits more than one electron, if the secondary
  • Mechanical Improvements on the Main Magnet for CYCIAE-14
  • The main magnet and main vacuum system of CYCIAE-14 have been installed and commissioned successfully. On this basis, relevant engineering experiences have been summarized, and the improvements have been made to optimize the current
  • Progress of CRARL in 2011
  • In 2011, the CRARL project mainly in commissioning phase, engineering staff in the leaders of support, in functional departments and the brother of unit under the assistance, under the leadership of general manager, by joint efforts to complete the main process equipment,
  • Progress on Radioactive Waste Treatment Facilities Construction
  • In 2011, five projects were undertaken by radioactive waste projects management department, which are “Cold Commissioning of the Pilot Project on Radioactive Waste Retrieval and Conditioning (abbreviation ‘Pilot Project‘)“, “Radioactive Ventilation Project Construction (abbreviation ‘Ventilation
  • Tensor Effect on Proton Bubble Structure of ~(46)Ar
  • We have calculated the proton density distribution of 46Ar for different pairing interactions with the Skyrme interactions SLy5 and SLy5+Tw (Tw is the tensor force, which was obtained by the G-matrix calculations and added perturbatively into the SLy5 interaction
  • Shell Model Study on the Proton Pigmy Dipole Resonances in ~(17, 18)Ne
  • The proton pygmy dipole resonances (PDRs) in proton rich nuclei 17, 18Ne have been investigated in the framework of interacting shell model. The shell model with the self-consistent Skyrme-Hartree-Fock wave functions has well reproduced
  • Microscopic Effective Charges and B(E2) Values of Terminating States in Mirror Nuclei ~(51)Mn and ~(51)Fe
  • The effective charges are commonly used in the restricted shell model calculations. In the pf shell, an agreement on the isoscalar part is reached to be around 2.0e, however the isovector part is still under the intense debate. Since wave function of terminating states is more pure
  • Fusion Reactions of ~(16)O+~(76)Ge and ~(18)O+~(74)Ge Near Coulomb Barrier
  • The fusion excitation functions of 16O+76Ge and 18O+74Ge at near-barrier region are measured, to research the positive Q-2n effect on the fusion reaction. The properties of the lower excited states are similar for the two targets. For neutron transfer channels,
  • High-Spin States in ~(86)Sr
  • The previous works for high spins states of 86Sr were very scarce. In the past, the spin of highest level of 86Sr was 13 found by the reaction 84Kr(α, 2nγ)86Sr in 28 MeV. The current work updates the level scheme of 86Sr to get more information about high spin states in 86Sr.
  • High-Spin States in ~(87)Sr
  • The number of protons and neutrons of nuclei in the A=80-90 region are between 28 and 50. The nuclei in 38 protons have a large deformation shell. The structure of these nuclei shows some information about intense competition between collective motion and single particle motion.
  • Fast Timing: Lifetime Measurements With LaBr_3 Scintillators
  • The lifetime of the first excited 2+ state in well deformed nuclei of the rare earth region is typically in the range of 1 nanosecond. A variety of experimental methods have been developed for such measurements. In addition to the recoil distance
  • Technique of Measuring Effective LET in Integrated Circuit (IC)
  • LET is one of the important parameters in the ground single event effects (SEE) simulation experiment results, the accuracy will directly affect the accuracy of evaluation of radiation ability of space-borne microelectronic devices. In past SEE experiments
  • Study on p+~(28)Si Reaction for Proton Single Event Effects Research
  • Single event effects is the one of the most importance space radiation effects. Therefore, it is very necessary pay a special attention to SEE. SEE can caused by a single heavy-ion traversing a semiconductor or semiconductor-based device
  • Immunofluorescence Detection of γ-H2AX Foci Induced by ~7Li Ions and γ-rays Radiation
  • DNA double strand breaks (DSBs) are considered as the most critical type of lesions. Correct and complete repair of DSBs guarantees cellular survival, while incorrect repair and residual DNA damage may lead to cell killing, mutation or transformation. Following induction of DNA double strand breaks,
  • Research of Fast Neutron Radiation Effect on Rats
  • In order to research the fast neutron radiation effect on rats,the 8 weeks Wistar male rats were wholly irradiated by 14 MeV fast neutron with 5 Gy. In the experiment,the rats were divided into normal and irradiation group, and killed
  • Test of RPC Detector by Cosmic Ray
  • RPC is a gas detector made of high resistive material, which aims at detecting the track and time of high energy charged particles. The RPC tested in this report will be used in the RHIC/PHENIX set-up forward upgrade. In this test,
  • Calculation for Single Spin Asymmetry of Neutral Pion in Polarized Protons Collision at 200 GeV
  • The single-spin transverse asymmetry for neutral pions Run-08 pp has been measured. We consider the recent RHIC data on the transverse single spin asymmetry (SSA) AN. The measurement is consistent with a vanishing SSA. The present preliminary results of π0 all measurements in polarized proton-proton
  • GEM Detector Electric Field Simulation
  • GEM (Gas Electron Multiplier) detectors have been widely employed in the experimental field of high energy physics and nuclear physics. As a successor to drift chambers, GEMs are much easier to fabricate and have a much higher spatial resolution
  • Progress in Measuring ~(238)U(n, xnγ) Cross Sections With HPGe Detector Array
  • Since the detector system had run for several years, so we did a overall maintenance and repair in order to optimize the performance. The frame of detector array was altered, so the detector can get closer
  • Design of Pre-collimator System for Neutronics Benchmark Experiment
  • In order to carry out evaluation of neutron nuclear data, in the last “Five-Year“ period, China Institute of Atomic Energy has developed a set of neutron nuclear data benchmarking test system, and used the time-of-flight technique to measure the neutron
  • Study of Fast Neutron Background Detection at Deep Underground Laboratory
  • In order to detect very low flux neutron background at deep underground laboratory, a low background fast neutron detector will be developed. The detector is a Gd loaded liquid scintillator contained in a Φ30 cm×40 cm cylindrica
  • Calibration of Li-glass Detector Efficiency
  • Li-glass detector will be used to measure the flux of neutron beam in Gamma-ray Total Absorption Facility(GTAF). We have calibrated the detection efficiency of Li-glass detector in 5SDH-2 accelerator. The beam of neutron was produced by the reaction 7Li
  • Lifetime Measurement of Inner Shell in the Collision of Fe, Au Ions and C Foil
  • The deep study of matter structure problem is very important and becomes an important guarantee of performance of nuclear weapon. In our county, some groups have done the inner-shell study and obtained some progresses, however most
  • Phase Stability of Intermetallic Compound Ce_3Al in Mechanical Milling
  • For many years, cerium-aluminum systems have been extensively studied because of their unusual magnetic behaviors. As atomic radii of cerium and aluminum differ greatly from each other, a solid solution is not obtained due to the Hume-Rothery rule.
  • Renewal and Modified Evaluation Data of ~(233)U in CENDL_-3.1
  • A complete set of evaluated neutron nuclear data of 233U was preformed before 2000, and released in 2009. The status of the published nuclear data 233U in CENDL-3.1 is in some cases not up to the requirements. As the recent experimental data
  • Uncertainty Analysis for Neutron Leakage Spectrum of LLNL Pulsed Sphere Facility due to Fission Cross Sections of ~(235)U
  • The uncertainty of basic nuclear data has become the main source for the uncertainty of integral parameters of nuclear facility. Thus, the study of such uncertainty plays an increasingly important role in nuclear design and simulation, especially in
  • Calculation of Prompt Fission Neutron Spectra for ~(235)U (n,f)
  • The prompt fission neutron spectra for neutron-induced fission of 235U at En<5 MeV are calculated using the nuclear evaporation theory with a semi-empirical model, in which the non-constant temperature and the constant temperature related to the Fermi gas model
  • Systematic Characteristics of Fast Neutron Fission Cross Sections for Actinide Nuclei
  • The neutron fission cross sections of actinide nuclei are important data for the design of nuclear reactor and nuclear engineering, and so on. So far, there has been a certain amount of experimental data for the fission cross sections of actinide nuclei. However,
  • Benchmarking ~(232)Th Evaluations With KBR and Thor Experiments
  • The n+232Th evaluations from CENDL-3.1, ENDF/B-Ⅶ.0, JENDL-3.3 and JENDL-4.0 were tested with KBR series and THOR benchmark from ICSBEP Handbook. THOR is Plutonium-Metal-Fast (PMF) criticality benchmark reflected with metal thorium.
  • Study on the Processing Method for Resonance Self-shielding Calculations
  • We investigate a new approach for resonance self-shielding calculations, based on a straightforward subgroup method, used in association with characteristics method. Subgroup method is actually the subdivision of cross section range for resonance energy range.
  • Research on Nuclear Reaction Network Equation for Fission Product Nuclides
  • Nuclear Reaction Network Equation calculation system for fission product nuclides was developed. With the system, the number of the fission product nuclides at different time can be calculated in the different neutron field intensity and neutron energy spectra
  • Iso-spin Dependent Microscopic Optical Model Potential Based on Dirac Bruckner Haretree Fock Method
  • The microscopic optical model is investigated in the Dirac-Brueckner-Hartree-Fock (DBHF) framework with Bonn B meson exchange potential. Both real and imaginary parts of isospin-dependent self-energies are derived from a strict projection
  • Preparation of ~(64)Ni-Gd-Cu Target
  • The three-layer-sandwich targets of 64Ni-Gd-Cu needed in the physics experiment were prepared. The middle layers are thin ferromagnetic Gd layers of about 1.7 mg/cm2, recoil stopper layers are thick crystallized and defect-free Cu layers of about 12
  • Preparation of Super-Thin, Large-Area, Double-Sided Gold-Plated Mylar Film
  • Large-area multi-wire parallel plane avalanche counter (MWPPAC) is a kind of gas detector widely used in nuclear experiments. MWPPAC is composed of front-window film, X wires, anode film, Y wires and rear-window film, which is mostly utilized to measuring
  • Post Accelerator for Proposal of CARIF
  • CARIF is a new generation ISOL-like RIB facility which is based on CARR, will be used to generate ions near n-rich line. Primary beam comes from CARR, separated and highly charged by ECRIS system, will be accelerated to 150 MeV/u, then works as bomb
  • Reliability Test of an ECR Ion Source for Accelerator Driven Sub-critical System (ADS)
  • The reliability of accelerator for ADS research is close to 100%, so the requirement for ion source is very high. Due to the high heat power and complicated environment such as the strong electric field, magnetic field and unfavorable vacuum condition nearby the extraction area,
  • Development of ECR Ion Source for ADS
  • A high-current microwave proton ion source for ADS research is being developed at China Institute of Atomic Energy. The RFQ input beam requirements are 75 keV, 60 mA proton current, 0.20π mm·mrad rms normalized emittance, and the reliability close to 100%.
  • Installation and Trial Run of the Furnace
  • In order to meet the demand of neutron experiment in the future, the neutron lab equips with extreme temperature furnace (Fig. 1), the furnace is designed and produced by the professional producer-Scientific
  • Progress in Neutron Texture Diffractometer at CARR
  • The key components for neutron texture diffractometer (NTD) at CARR, such as the collimator monochromator and the neutron beam limiting systems, have been finished in the year 2011. At the same time, improvements of the detector shielding and controlling software were finished.
  • General Design for CARR Neutron Guide System
  • A neutron guide system has been designed and partly installed at the China Advanced Research Reactor (CARR) to transport cold neutrons from the cold neutron source (CNS) to several instruments,which are situated in a separate guide hall of 30 m×60 m.
  • Experimental Software Design of the Neutron Texture Diffractometer at China Advanced Research Reactor
  • Neutron scattering lab is building our country‘s first neutron texture diffractometer, which will be used for the texture measurement and analysis in the materials science and engineering applications. The sample table and its measurement and control
  • Floating Zone Growth of LiFePO_4 Single Crystals
  • During the past few years the search for cathode materials of rechargeable lithium batteries has been mainly focused on lithium metal oxides. Among them, lithium iron phosphate, LiFePO4, provides an attractive voltage of 3.5 V, high theoretical capacity
  • H_3~(10)BO_3/ZnS(Ag) Scintillator Screen for Thermal Neutron Radiography
  • In 2011, neutron image team has completed the fabrication work of the scintillator screen for thermal neutron radiography. The neutron converter screens consist of a dispersion of H310BO3/ZnS(Ag) particles in epoxy binder. H310BO3/ZnS(Ag) screen with
  • Non-destructive-Testing of Nuclear Fuel Element by Means of Neutron Imaging Technique
  • Nuclear fuel element is the key component of nuclear reactor. People have to make strictly testing of the element to make sure the reactor operating safely. Neutron imaging is one of Non-destructive-Testing (NDT) techniques, which are very important techniques for
  • Crystal Structure and Thermal Expansion Properties of Lu_(2-x)Fe_xMo_3O_(12)
  • Low or zero thermal expansion materials have a lot of potential applications in space shuttle, microelectronic components, and optical mirrors et al. Polycrystalline samples Lu2-xFexMo3O12 have been prepared successfully by solid state reaction,
  • Neutron Time of Flight Spectrometer for Velocity Selector Calibration
  • Small angle neutron spectrometer on China Advanced Research Reactor (CARR) is located at neutron guide hall and is installed on the end of cold neutron guide. Velocity selector which can purify white light neutron beam into monochromatic neutron beam with wavelength
  • Progress Report of Small Angle Neutron Scattering on CARR
  • The project of small angle neutron scattering spectrometer (SANS) belongs to “building up the center for neutron scattering“. It‘s one of the project “national science & technology infrastructure center“. The building parts are already done in 2010. By the proposal one of
  • Small Angle Neutron Scattering Study on Structure of PAMAM Dendrimer Encapsulation With Small Molecules in Aqueous Solution
  • Dendrimers have very unique structural and physicochemical properties and many potential important applications, such as drug delivery, and therefore have been attracting research interests. It is interesting and important to investigate the interaction of
  • Investigation on Crystal Structure, Magnetism and Colossal Magnetoresistance of Y_2CrS_4
  • Ternary yttrium chromium sulfide, Y2CrS4, was well prepared by a solid state reaction of Y2S3, Cr, and S. In this year we investigated its crystal structure, magnetism and magnetotransport properties. The X-ray diffraction pattern at 300 K was refined with
  • Study on Different Forms of Calcium Metabolic Behavior in Normal and Osteoporosis Rats by ~(41)Ca Tracing
  • Because of calcium deficiency,there were about 90 million Chinese people suffering from osteoporosis which caused a great calcium supplement boom in 2009. However, recent studies have shown that excess calcium supplement may cause some other diseases
  • Discussions of Chemical Extraction Methods for Iodine-129 Determinations Using AMS System
  • As the longest-lived radioisotope of iodine with a half life of 15.7 Ma, Iodine-129 is widely used as a tracer in various environmental practices such as monitoring of nuclear environmental safety, seawater transport, and dating of
  • Superheated Droplet Detector Response for Temperature
  • Superheated droplet detector has the following advantages: Used repeatedly, recording the cumulative dose, using both indoors and outdoors, compacting; relatively low cost, direct reading of the bubbles using the naked eye, and working in gamma-neutron mixed-field well
  • Key Issue of Ultra-trace Environmental Samples by ~(236)U/~(238)U-AMS Method
  • The accurate determination of uranium-236 in samples at ultra-low level is critical. Combined with AMS , reducing the background effects throughout the experiment is quite necessary. Therefore, some advances on the determination of 236U by accelerator mass spectrometry
  • Suppression Factor of ~(182)W for ~(182)Hf AMS at CIAE
  • Suppression factor of 182W is an important index in the measurement of 182Hf with AMS method. This factor is defined as the value of 182W/180Hf in blank samples divised by the measured value of 182 W/180Hf with AMS method. In order to satisfy a
  • Study on Different Samples in Measurement of Manganese-53 With AMS
  • 53Mn is mainly produced by nuclear reaction of cosmic rays on iron with a half-life of 3.7 Ma. Because it has the potential to allow dating test range to >10 Ma, it is a very useful nuclide to determine various geomorphological parameters
  • Design of Stopper of Prompt Gamma Neutron Activation Analysis Facility at China Advanced Research Reactor
  • The PGNAA facility consists of the filtered collimated neutron beam, the shielding of the whole facility, the control system, the detecting equipment and the data acquisition and analysis system. The neutron beam is filtered by a mono-crystalline bismuth filter,
  • Preliminary Study on the Determination of ~(235)U and ~(239)Pu Using Delayed Neutron Counting Method
  • The preliminary study on the fast measurements of 235U and 239Pu in samples containing 235U, 239Pu and 235U-239Pu mixture using delayed neutron counting method is introduced. All samples were irradiated for 30 s using the 30 kW Miniature Neutron
  • Radiation Effect of CLAM Steel by Triple Ion Beams Irradiation
  • The CLAM steel is a self-developed low activation martensitc steel of china. Its alloy composition is Cr-8.91%, W-1.44%, V-0.20%, Ta-0.15%, Mn-0.49%, C-0.12%, S-0.003%, Si-0.29% and Fe balanced to 100%. This steel is considered as one of the
  • Investigation of H-Pd, H-PdAg and H-PdY Alloy Systems by Positron Annihilation Lifetime Spectroscopy
  • In present work the defects induced by hydrogen in Pd, Pd0.75Ag0.25 and Pd0.92Y0.08 (in weight) were investigated as a function of hydrogen concentration by the positron annihilation lifetime method. The Pd, Pd0.75Ag0.25 and Pd0.92Y0.08 (in weight) samples were
  • A SSS Spectrometer
  • The SSS spectrometer, so called simple scintillation spectrometer, is made by BTI (Bubble Technology Industries). The spectrometer can be used in the neutron energy range from 4.0 to 17 MeV. The SSS includes two sections: A probe and an analyzer module
  • Construction Design of Tissue-Equivalent Proportional Counter
  • Mechanical and electrical design of tissue-equivalent proportional counter is strongly interdependent. Each aspect of design places restrictions on the other, such as the selection of materials, detector reliability, performance characteristics, and assembly.
  • Manufacture of Single ~(60)Co Source Irradiation Facility
  • Reference radiation filed produced by isotope source is necessary for calibration of radiation dose meter. According to the GB/T 12162.1-2002 “X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining
  • Recent Progress in Research on Microcalorimeter for Radioactivity Measurement of Tritium
  • A twin-cup heat-flow microcalorimeter is ongoing development for tritium measurement in frame of programme of TBM online production, measurement and analysis of tritium. In order to maintain stable temperature in the calorimeter cell,
  • Recent Progress in Liquid Scintillation Counting System for Absolute Radioactivity Measurement
  • The triple to double coincidence ratio (TDCR) method is an absolute activity measurement method in liquid scintillation counting, especially developed for pure β- and EC-emitters activity standardization. Such a liquid scintillation counting system is now
  • Design of Radioactive Reference Barrels and Simulation Verification of Linear Source
  • Shell source method was used to prepare radioactive reference barrel for the calibration of gamma scan device because filling method in normal ways produces “hot“ points easily and decrease the safety in transportation of the barrel.
  • Study of Preparation of Large Area Standard Source
  • With increasingly widespread application of nuclear technology, many large area contamination detectors are used to measure the contaminated surface by α, β radionuclides in nuclear facilities and isotope production places. To solve the
  • Development of Nanosecond Short Pulse High Power KrF Laser System
  • Compression of short pulse laser is demanded by the physical experiments such as EOS for Heaven-I system. A nanosecond short pulse high power discharge pumping excimer laser system was developed under the frame of Science and Technology
  • Experimental Study on Planarity of Shock Waves Driven by High Power Eximer Laser Pluses
  • For the two types of targets in these experiments, a one-dimension three-temperature hydrodynamic simulation code HYADES was used to optimize the target parameters and to make sure the results of two types of targets can be compared with each other.
  • Energy Spectrum of Protons Driven by Ultra-short Laser Interaction With Thin Gold Foils
  • Proton acceleration experiments by irradiation of an ultra-short laser with gold foils of 5 and 2.1 μm thickness were investigated. The laser system produced pulses having energies of up to 11 mJ at a wavelength of 744 nm with a temporal duration of 120 fs,
  • Influence of Laser Prepulse in Ultra-short Laser-Driven Proton Acceleration
  • Influence of laser prepulse in ultra-short laser-driven proton acceleration was investigated by the differences in spatial distribution and energy spectrum between different foil-targets. The laser system produced pulses having energies of up to
  • Proton Acceleration Drived by High-intensity Ultraviolet Laser
  • The generation of energetic protons from a solid thin-foil by the interactions of ultra-short and intense laser pulses is investigated in numerous experiments in the last decade. The energetic proton beams are promising candidates for proton fast ignitor (PFI)
  • Plasma Expansions With Time-Dependent Electron Temperature
  • The fundamental of ion acceleration from the laser-solid interactions is the theory for describing plasma expansions into a vacuum. In the time interval of tens of femtoseconds after the laser pulse reaches the target, the plasma reaches
  • Investigation of Isotope Separation Utilizing Spontaneous Magnetic Field of Ultra-Short Laser Pulses
  • A piece of boron (B) film grows on copper (Cu) floor along the normal of B target in the interaction of solid B target with Infrared laser of 120 fs pulse duration and 7 mJ energy. Analyzing B isotope distribution on Cu floor by SIMS (second ion mass spectrum)
  • Calculation for Improvement of 350 keV Electron Accelerator
  • The main problem of the 350 keV electric accelerator is that the accelerator can not output 20 mA for a long time otherwise the vacuum become bad. The reason is that part of the beam bomb on the scanning box and increase the temperature immediately,
  • Research of Elements for Beam Redistribution
  • Particle beams with uniform and well-confined intensity distributions are desirable in some high power beam applications to prolong the target lifetime or to improve the beam utilization. Three kinds of elements had been proposed for the beam homogenizing,
  • Dynamics Calculation of CH-DTL
  • CH-DTL is a new development of accelerator structure, which has high shunt impedance and simple structure. The beam dynamics of CH-DTL is based on KONUS method, whose characteristic is that the longitudinal focus is small or none,
  • Dynamics Calculation of Spoke
  • Compared with ellipse cavity, the spoke cavity has many advantages, especially for the low and medium beam energy. It will be used in the superconductor accelerator popular in the future. Based on the spoke cavity, we design and calculate an accelerator
  • Dynamics Calculation of Travel Wave Tube
  • During the dynamics calculating of the travel tube, we must obtain the field map in the tube. The field map can be affected by not only the beam loading, but also the attenuation coefficient. The calculation of the attenuation coefficient
  • Calculation of Uniform of Beam Scanning
  • For the electron beam application, it is always scanned by a dipole magnet. The uniform of the scanning has great influence for some application, such as the irradiation of the thyristor. There are two methods for improving the scanning uniform:
  • Design of Cavity for 10 MeV Electron Irradiation Accelerator
  • This article describes the 10 MeV high-power electron irradiation accelerator. This accelerator can output varied energy electron beam which the highest energy is 10 MeV or shooting target produce X-rays for industrial radiation processing.
  • Research of Quick-Response Protective System for Klystron of Multi-Energy Electron Linac
  • Multi-energy electron linac could be widely used in nondestructive testing, vehicle inspection, industrial irradiation and other fields. One of its key components is a klystron which is very expensive. In commissioning or operation,
  • UHV Vacuum System R&D of Multi-energy Electron LINAC
  • The multi-energy electron LINAC was an experimental device developed for irradiation metrology, the vacuum system is a main part of the device to maintain a low pressure. The accelerator tube is made of copper and the vacuum chamber is almost entirely made of stainless steel.
  • Self Shielding System R&D of 350 keV High-Voltage Electron Accelerator
  • A 350 keV high-voltage electron accelerator was developed for irradiation of plastic film products. The accelerated electron beam is extracted into an atmosphere through the titanium outlet window to the plastic films on the pipeline. For the X-ray beam is
  • Nuclear Fuel Solution System Transient Analysis
  • The fissile material exists as solution in the process of the nuclear spent fuel reprocessing. The dissolved fissile material is well moderated and usually the system can be critical with limited amount of fissile material; solution can be changed to any
  • Consultative Report on NPP Improving Loading Factor
  • Compared with other advanced nuclear power plants about operation performance, we analyze the critical factor that have the negative impact in improving the loading factor of the nuclear power plants that belong to China Nuclear Union Company and summary the experience.
  • Study Report of Design Guide for Tube Arrays in Cross Flow
  • Part of fluid energy transfers to the cylinders, when the fluid flows away the cylinders, and creates the vibration of them. The vibration of cylinders caused by the cross flow is much more violent than that caused by axial flow. So the sufficient concern should be given
  • Study Report of Design Guide for Single Circular Cylinder in Axial Flow
  • The vibration of a flexible cylinder in axial flow is random, so the quantities of interests are the root-mean-square value of the response and the amplitude distribution. This design guideline presents a relationship for calculating the
  • Study Report of Design Guide for Single Circular Cylinder in Turbulent Cross Flow
  • There are many structures similar as circular cylinders in cross flow in reactors and strong fluid excitation may exist. Therefore the associated response must be accounted for in fatigue or fretting and wear design. The character and
  • Numerical Model Analysis of Fluid-Elastic Instability of Thin Rectangular Plate Due to Overflow
  • A circular thermal baffle weir is located close to the main vessel of liquid sodium cooled pool type fast breeder reactors (fast reactor for short thereafter). During operation of the fast reactor, a little part of liquid sodium flows from
  • Small Punch Test on Before and Post Irradiated Domestic Reactor Pressure Steel
  • Problems may be caused when applying the standard specimen to study the properties of irradiated reactor materials, because of its big dimension, e.g.: The inner temperature gradient of the specimen is high when irradiated, the radiation
  • Status of R&D on Tritium Permeation Barrier Coatings for Tritium Breeding Blanket of Fusion Reactor
  • The paper overviewed the recent progress in the application of several typical tritium permeation barrier (TPB) coatings and their corresponding fabrication technologies for tritium breeding blanket of fusion reactor. According to the design requirements of
  • Failure analysis for JNK Boracic acid Tank Room of NPP
  • The JNK Boracic acid Tank Room is important safety equipment for Nuclear Power Plant. Corrosion,crack and leaked Boracic acid were found on the some welding area of the liners of the JNK Tank Room during operation.
  • Piping Stress Analysis of Secondary Cooling Water System in CARR
  • Some piping valves of China Advanced Research Reactor (CARR) cannot maintain the leak tightness when debugging. Because the valves need to be exchanged, the stress analysis and evaluation should be made for the piping with new valves in order to make sure whether
  • Stress Assessment of Security Injection Tank
  • The purpose of the calculating is to make the stress assessment of the security injection tank according to the requirements of the code and the designing on the basis of the gained results of the static, the seism and the thermal stress in order to judge
  • Thermal Stress Analysis of Security Injection Tank
  • The purpose of the thermal stress analysis of the security injection tank is to make sure whether the tank can withstand the concerned thermal load or not on all the conditions conforming to the concerned code prescripts and the design requirements.
  • Anchor Stress Checking of Security Injection Tank
  • The intention of the calculating is to check the anchor stresses of the security injection tank to know whether the stress is satisfied the code requirements on the basis of all the reaction forces gained in the static, seismic and thermal stress results.
  • Static Stress Analysis of Security Injection Tank
  • The static structural analysis of the security injection tank is made to make sure whether the tank can withstand concerned loads or not on all conditions conforming to concerned code prescripts and design requirements. The tanks
  • Seism Analysis of Security Injection Tank
  • The purpose of the seism analysis of the security injection tank is to make sure whether the tank can resist the concerned dynamic loads or not on all the conditions according to the concerned prescripts of the code and the design requirements.
  • Buckling Analysis of Supporting Skirt of Security Injection Tank
  • The purpose of the calculating is to make a structural buckling analysis according to the code rules and the design requirements in order to judge whether the security injection tank have the ability to resist the buckling failure or not
  • Radiation Measurement for Ji Nan MNSR Decommissioning
  • Ji‘Nan MNSR is an under moderated reactor of pool-tank type, UAl with high-enriched 235U as fuel, beryllium as reflector, and light water as coolant. It was built in 1989, and shutdown in 2008. It operated 840 times, the total operation time is 3 194.
  • Preliminary Design of Special Unloading Tool for Miniature Neutron Source Reactor
  • In recent years, MNSR (Miniature Neutron Source Reactor) LEU conversion is appreciated by IAEA and the related country, and CIAE is also carrying out this work. In the process of MNSR LEU conversion, unloading for the HEU fuel is an important work,
  • DAQ System of Current Based on MNSR
  • The flux or power should be acquired using the detector in the operation of MNSR. As usual, the signal of detector is current, and it is very width range with 10-11-10-6 A. It is hard to satisfy the linearity to amplify this signal by using fix gain
  • Preliminary Research of Neutron Energy Spectrum of Thermal Neutron Beam Port for IHNI
  • IHNI with 30 kW is specially designed for Boron Neutron Capture Therapy (BNCT), it is the pool-tank reactor, UO2 with enrichment of 12.5% 235U as fuel, beryllium as reflector, light water as moderator and coolant. There are two neutron beams in the opposite side
  • Study on Anode Process in Molten Salt Electrolysis of CeO_2
  • The electrometallurgical treatment of spent metallic fuel, which is the most promising pyrochemical reprocessing process, was pursued intensively. In order to extend the electrometallurgical treatment technology to spent oxide fuels,
  • Concentration Determination of Tetravalent Uranium by Direct Spectrophotometric Method
  • The traditional concentration determination method of macro amount of tetravalent uranium in aqueous solution is potassium dichromate titration which is simple to operate with high accuracy and big volume of effluent. In order to simple
  • Determination of α Dose Rate of ~(238)Pu Solution
  • In order to study the radiolysis effect of α particles to reagents and understand the chemical process in reprocessing process, we measured the α dose rate of 238Pu solution by the method of Fricke dosimeter. The absorbing dose can be calculated by the formula:
  • Preparation of Uranous Nitrate by Membrane Electrolysis
  • U(Ⅳ) is a main reductant used in the Purex process. Electrochemical method is a sound way to prepare U(Ⅳ) due to it is easy to control and monitor the produce process and not using other additives. However, in traditional electrochemical method, U(Ⅳ) yield is usually between 60%-70%.
  • Research of Trend of Technetium in U/Pu Partition Step of APOR Process
  • In U/Pu partition step of APOR process (1B tank), where monomethylhydrazine (MMH)- dimethyl- hydroxylamine (DMHAN) are adopted as reductants, most of technetium flows into 1BP, but the reason remains unclear. Our work explains this phenomena through
  • Extraction of Np(Ⅳ, Ⅴ, Ⅵ) Ions From Aqueous Nitric Acid Solutions With TODGA and DHOA
  • Two novel extraction reagents, N, N, N , N′-tetraoctyl diglycolamide (TODGA) and N, N-dihexyl- octamide (DHOA) have been used as extractants for extraction Np(Ⅳ, Ⅴ, Ⅵ) ions from aqueous nitric acid solutions. The effects of concentration of the nitric acid
  • Valance Adjustment of Np and Pu in 1AF Fluid of Pilot Plant
  • The influence of temperature and time on Np(Ⅵ ) and Pu(Ⅵ ) percent in 1AF fluid had been studied, the constitute of 1AF fluid was followed as: c(HNO3)=2 mol/L, (U)=225 g/L, (Pu)=2.4 g/L, (Np)= 0.129 g/L, which was in accord with the pilot test
  • Study on Extraction Performance of Tri-iso-amyl Phosphate
  • The distribution performance of HNO3, Pu(Ⅲ ), Pu(Ⅳ) and Np(Ⅳ) in the two phase system of Tri-iso-Amyl Phosphate(TiAP) and aqueous, the influence of the concentration of extractant, nitric acid and Al(NO3)3 on the distribution ratio of Pu(Ⅲ ),
  • Catalytic Reduction of U(Ⅳ) With Hydrazine in Nitric Acid Solutions
  • Preparation of U(Ⅳ) in heterogeneous-catalytic processes is a potential method that can react in normal temperature and pressure and the process is very simple. The reduction of U(Ⅵ) with hydrazine catalyzied by platinum black or Pt/SiO2 in HNO3
  • Determination of Trace Plutonium in Uranium Product by ID-ICP-MS
  • Plutonium is strictly limited in the uranium product of spent fuel reprocessing. The analysis of plutonium in uranium product is the key point of product quality control. Plutonium concentration is limited below
  • Determination of Micro U, Np, Pu by Highly Oriented Pyrolytic Graphite Pre-diffraction EDXRF
  • Based on the prototype of Highly Oriented Pyrolytic Graphite Pre-Diffraction EDXRF, a new device was constructed after optimizing of hardware including high voltage supplier, detector, sample bracket, and software of data processing.
  • Analytical Instrument of X-ray Fluorescence Determine Concentration of U and Pu in Organic Solution at the Same Time
  • An instrument is developed to measure the concentration of U, Pu and the intensity of gamma ray in samples of 1AP organic phase at the same time. The Ag cold cathode is used to excite L series X-ray fluorescence of U and Pu. The Si-pin detector is
  • U(Ⅳ) Preparation by Method of Electrolysis
  • U(Ⅳ) is prepared by electrolysis of U(Ⅵ) in nitric acid, as showed in Fig. 1. A circular-sheet osmotic film is fixed at the middle of electrolytic cell. Osmotic film can urge the electron transfering from one pole to another, but electrolyte
  • Separation and Purification of Fissiogenic Ruthenium From Irradiated Uranium
  • Ruthenium is an important fission product. Its isotopic composition may reflect the burnup or the initial uranium enrichment of nuclear fuel. So the separation and purification method of fission products of Ruthenium from irradiated uranium was studied and established.
  • Development of an Analytical System for Determination of Free Acid via a Joint Method Combining Density and Conductivity Measurement
  • Determination of free acid plays an important role in spent nuclear fuel reprocessing. It is necessary to develop a rapid analytical device and method for measuring free acid. A novel analytical system and method was studied to monitor the acidity
  • Development of an Analytical System for Rapid, Remote Determining Concentration and Valence of Uranium and Plutonium
  • Concentrations and valence of U and Pu directly shows whether the Purex process is under normal conditions or not. It is necessary to monitor concentrations and valence of U and Pu in real-time.Purposes of this work is to develop an analytical
  • Study of Multi Total Reflection X-ray Fluorescence Spectrometer
  • A total reflection X-ray spectrometer was set up, in which Mo tube was used as excitation source, Zr with the thickness of 100 μm was as filter, and λ/20 glabrous silicon was as reflector, λ/100 glabrous silicon was as sample carrier.
  • Study Progress of On-line Monitoring Device for Uranium and Plutonium by XRF
  • An X-ray fluorescence spectrometer was designed and set up, which was used to determine uranium and plutonium on-line in reprocessing process stream. Uranium in aqueous and organic phase, plutonium in aqueous were measured by using the device,
  • Study on Radiochemical Separation and Measurement of Half-life of ~(88)Kr
  • 88Kr is one of the important gaseous fission products for determining the burn up of nuclear fuel with a short half-life, high fission yield and high branch ratio of γ-ray. Due to the more uncertainty of evaluated data and rare experimented data,
  • A Method for Determination of ~(99)Tc in Soils Using TEVA Resin
  • 99Tc is an artificial long-lived pure beta emitter with maximum beta particle energy of 292 keV. It is produced with high yield (~6%) during nuclear fission of 235U and has a radiological implication and environmental risk. In aqueous solutions,
  • A Convenient Method for Synthesis of 2-allyloxymethyl-18-crown-6
  • Extraction chromatography has been proven a sufficient method for the isolation of 90Sr from large quantities of inactive matrix constituents and from a number of interfering radionuclides. The commercial Sr-SpecTM resin was made of
  • Determination of Stability constant of Coordination Reaction of 2-allyloxymethyl-18-crown-6 with Sr~(2+) in Water
  • Strontium-90 is one of the most concerned radionuclides in environmental radiochemistry. Numerous methods have been described for the determination of radiostrontium in biological and environmental samples. An essential step in all of these methods
  • Study on Performance of Empore~(TM) Technetium Rad Disks
  • EmporeTM Technetium Rad disks produced by 3M Company contain GD-1 sorbent loaded on particles that are embedded in an inert PTFE matrix. In this study, several experiments have been accomplished to evaluate the performance of EmporeTM Technetium Rad disks.
  • Study on Performance of Empore~(TM) Strontium Rad Disks-Ⅱ
  • EmporeTM Strontium Rad disks produced by 3M Company contain a strontium-selective crown ether extractant loaded on silica particles that are embedded in an inert PTFE matrix. The disks allow aqueous solutions to pass through in high flow rate. It makes
  • Sequential Separation of U, Np and Pu From Environmental Samples
  • Affected by nuclear testing and nuclear reactor accidents, the release of radioactive substances into the environment, especially long-lived radionuclides including U, Np and Pu can cause great harm to the environment, ecology and
  • Separation of Uranium From Spent Fuel Solution in Burnup Measurements Process
  • In order to establish an automatic radiochemistry separation procedure of U from spent fuel solution, a method of separating U quickly and effectively from the feed solution is needed. TBP exctraction chromograph method had been adopted
  • Separation of Molybdenum From Spent Fuel Solution in Burnup Measurements Process
  • In order to establish a kind of automatic radiochemistry separation procedure of nuclide 100Mo from spent fuel solution in burnup measurements process, a method of separating Mo quickly and effectively from the feed solution is needed. In the studies,
  • Content of Transuranium Nuclide in Process of Irradiating Thorium
  • Currently, sufficient nuclear fuel supply is most important problem with the nuclear power grow rapidly, so the use of thorium fuel is being put on the agenda. The applicability of thorium as a power reactor is based on a (n, γ) reaction on 232Th. The consequent nucleus, 233Th,
  • Morphology Characterization of Uranium Particles From Laser Ablated Uranium Materials
  • In the study, metallic uranium and uranium dioxide material were ablated by laser beam in order to simulate the process of forming the uranium particles in pyrochemical process. The morphology characteristic of uranium particles and the surface of
  • Studies on Measurement of Impurities in Uranium Sample
  • The impurities of nuclear material produced by different factory usually has its characteristic information which can be used to trace to the source of nuclear material.Because of the complexity of emission spectrum,uranium will
  • Monitoring Fallout From Fukushima, Japan After Nuclear Accident
  • In this work, on March 23rd, 2011, following the radioactivity releases after the nuclear accident in Fukushima, Japan, the first arrival of the airborne fission products 131I in Heilongjiang province the northeast of China, were detected
  • Preparation of Inorganic Sorbent KNiFC and Its Application
  • 137 Cs which has high fission yield about 6.14%, long half-life, and 661.7 keV γ-ray exists in 1AW, nuclear plant liquid waste, nuclear facilities decommissioning waste, radioactive lab liquid waste and other radioactive liquid waste. 137Cs can
  • Preparation of Inorganic Sorbent for Strontium and Its Application
  • 90Sr, which has high fission yield, long half-life, and β radiation exists in 1AW, nuclear plant liquid waste, nuclear facilities decommissioning waste, radioactive lab liquid waste and other radioactive liquid waste. 90Sr is of highly radioactive toxicity,
  • Destruction of Tributyl Phosphate and Exchange Resin by Electrochemical Oxidation
  • Spent tributyl phosphate and spent exchange resin are difficult to treat. It‘s important to develop an advanced treat method. Compared with traditional methods, electrochemical oxidation has obvious advantages, such as the operation can
  • Site Cleanup of Radioactive Isotope Container Rinsing Pool and Surrounding Environment
  • Radioactive isotope container rinsing pool and surrounding environmental site was a place of fabrication of container, and package, transportation and storage of radioactive isotopes. A heavy contamination existed in this area for burying of some radioactive wastes.
  • Biodistribution of ~(99)Tc~m Labelled Dextran Conjugates for Sentinel Lymph Node Detection
  • Mannosylated dextran conjugates showed high receptor affinity to the receptors on the surface of macrophages in the lymph node. 99Tcm labelled mannosylated dextran conjugates could be used for sentinel lymph node (SLN) detection. In this paper,
  • Preparation, Radiolabelling and Biodistribution Study of ~(177)Lu-DTPA-G3
  • Polyamidoamine (PAMAM) dendrimers are new artificial macromolecules with tree-like structure and have characteristics of greater water-solubility, bioavailability and compatibility. It can be carried by the drug molecules. PAMAM have been
  • Preparation and Biodistribution Evaluation in Mice of ~(177)Lu-DOTA-TOC
  • The study of 177Lu labeled radiopharmaceuticals for cancer therapy is fast emerging as an important part of nuclear medicine. 177Lu-labelling of DOTA derivatized peptide DOTA-TOC (Tyr3-Octreotide) was carried out and biodistribution of 177Lu-DOTA-TOC in normal
  • Determining Contents of Five Impurities in Cyclotron- Produced ~(64)Cu Solution by Emission Spectroscopy
  • 64Cu ( β+=17%, β-=39%, IEC=43%) is an important emerging biomedical radionuclide, which is useful for PET as well as a promising radiotherapy agent for the treatment of cancer. It can be produced on a small biomedical cyclotron utilizing 64Ni(p, n)64Cu nuclear reaction.
  • Determination of Medronic Acid and Its Related Substances by Reversed-Phase High-Performance Liquid Chromatography
  • An isocratic liquid chromatographic method with evaporative light scattering detection (ELSD) was developed for the determination of medronic acid and its related substance. Volatile pentylamine was used as ion-pairing agent. Separations were performend
  • Quantification of Kryptofix2.2.2 in ~(18)FDG by HPLC
  • 2-deoxy-2-[18F] fluoro-D-glucose (18FDG) is the most commonly used radiopharmaceutical for positron emission tomography (PET). Kryptofix2.2.2 (K-222) is used as a phase-transfer catalyst in the synthesis of 18FDG.Because of its toxicity
  • Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of Enrofloxacin
  • An up-converting phosphor (UCP) immunochromatography test was developed for the detection of enrofloxacin (ENR). The anti-ENR monoclonal was conjugated to the up-converting phosphor particles while the ENR-BSA immobilized on the nitrocellulose membrane
  • Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of Sulfadiazin
  • An up-converting phosphor (UCP) immunochromatography test was developed for the detection of sulfadiazine (SD). The anti-SD monoclonal was conjugated to the up-converting phosphor particles while the SD-BSA immobilized on the
  • Specific Activity and Impurities in Irradiated Natural Nickel Target
  • In this paper, the specific activity of the 63Ni which is produced by irradiating natural nickel in a nuclear reactor is calculated. And in the 1 g irradiated natural nickel target, the species of the key impurity nuclides were analyzed,
  • Determination of Two Columns Performance
  • When protein is analyzed by high performance liquid chromatography (HPLC), the selection of column is one of the most important factors. There are four quality control parameters for the column, which are theoretical plates n, capacity facto
  • Synchronizability Analysis of Harmonious Unification Hybrid Preferential Model
  • The harmonious unification hybrid preferential model uses the dr ratio to adjust the proportion of deterministic preferential attachment and random preferential attachment, enriched the only deterministic preferential network model,
  • Algebraic Condition of Nonlinear Dynamical Network Synchronization
  • Consider N linearly and symmetrically coupled identical dynamical systems, every node expresses a dimensional dynamics system.
  • Unified Hybrid Network Theoretical Model Trilogy
  • The first of the unified hybrid network theoretical model trilogy (UHNTF) is the harmonious unification hybrid preferential model (HUHPM), seen in the inner loop of Fig. 1, the unified hybrid ratio is defined.
  • Influence of Deterministic Attachments for Large Unifying Hybrid Network Model
  • Large unifying hybrid network model (LUHPM) introduced the deterministic mixing ratio fd on the basis of the harmonious unification hybrid preferential model, to describe the influence of deterministic attachment to the network topology characteristics,
  • Influence of Random Attachments for Large Unifying Hybrid Network Model
  • The large unifying hybrid network model (LUHNM) is the second model in the UHNTF, we calculated the relationship between the synchronizability of LUHNM and the gr ratio, the results are shown in Fig.
  • Uranium Enrichment Analysis With Electromechanical Cooled HPGe Detector
  • The Micro_trans_SPEC-100 portable high-resolution gamma-ray radioisotope identifier was used for the uranium enrichment analysis demonstration. Micro_trans_SPEC utilize stirling-cycle cooler and integrated detector, signal electronics and analysis
  • Development of Uranium Works Reference Sample for NDA Measurement
  • The works reference sample usually used in NDA instruments calibration, methods research and samples quantitative analysis. It is also can be applied in quality control as instruments performance checking and maintenance. In this work,
  • γ Ray Radioactivity Measurement of ~(88)Y and ~(22)Na Point Source
  • Both 22Na and 88Y have adequate half life, they are broadly used in radioactive measuring field. They are also very important in different techniques application and usually used in γ ray detectors like as high purity germanium efficiency calibration.
  • Study on Application of Mobile Radiological Monitor
  • The mobile radiological monitor has been applied for the radiation level of a nuclear facility in 2011. Based on the requirement, the monitor had been improved, it can measure and save the data of gamma-ray and neutron radiation level, the dose rate and the
  • Emission Data-Analysis of TGS Under Continual Scanning Mode
  • In the emission data-analysis of TGS under the continual scanning mode, we divide the efficiency matrix into two parts, one part has nothing to do with the measured sample, that is the intrinsic efficiency of the detector and the geometry efficiency of the system;
  • Transmission Data-Analysis of TGS Under Continual Scanning Mode
  • We choose the SART arithmetic to solve the problem of reconstruction of transmission image.
  • Nuclear Material Accountancy Assessment Technical Measures in Nuclear Centrifuge Enrichment Facility
  • Nuclear material accountancy assessment is the main technical measures for nuclear materials regulatory. It is an important basis to detect theft, loss and the illegal diversion of nuclear material. In order to implement the control of nuclear materials for nuclear facilities,
  • Study on Calibration of Device of Heterogeneous Matrix With Uranium inside
  • The device of measuring heterogeneous matrix with uranium inside is built base on ray segment scan technology and neutron analysis technology, to use to measure the heterogeneous matrix with Uranium inside which produced by chemical transformation
  • Software Development of Measurement System Heterogeneous Uranous Drums
  • Segmented Gamma Scanner (SGS) is a kind of important assay methodology of non-destructive assay (NDA). With the characteristic gamma ray, the mass or activity and nuclear species of measured material can be determined by the method. The software has the
  • Study on Automatic Control of Measurement System Heterogeneous Uranous Drums
  • Segmented gamma scanner (SGS) is a kind of important assay methodology of non-destructive assay (NDA). With the characteristic gamma ray, the mass or activity and nuclear species of measured material can be determined by the method.
  • Physical Protection System Effectiveness Evaluation Project
  • Whether the performance meets regulation requirements is a key point to physical protection system (PPS) of nuclear material and nuclear facility. To develop PPS effectiveness evaluation methodology and to use risk analysis based on Design Basis
  • Application Research of Developed Drummed Nuclear Waste Neutron Counting System
  • The application researches such as variety of factors affecting the measurement, calibrating etc. are need before the drummed nuclear waste neutron counting system (WNC) can be really put into use after installed at the site.
  • Development on New Style of Drummed Nuclear Waste Neutron Counting System
  • Designing a new style of drummed nuclear waste neutron counting system (WNC) was carried out in 2011. 3He proportional tubes are used as detector in this system. According to the limited quantity of 3He tubes, Monte Carlo method is used for
  • Supervisory Monitoring of Workplace at CIAE in 2011
  • 1 Introduction Based on The Routine Monitoring Programme for Workplace at CIAE in 2011 which approved by Division of Safe and Environmental Protection, a management sector of China Institute of Atomic Energy (CIAE), supervisory monitoring of
  • The Biokinetic Model of Americium
  • To improve in vivo measurements for detecting internal exposure from transuranium radio nuclides, such as neptunium, plutonium, americium, the bioknetic model was studied. According to ICRP report (1993, 1995, 1997) and other research, the
  • Research on Health Risk-Based Radioactive Acceptance Criteria of Municipal Solid Waste Landfill
  • The article focuses on the topics of Health Risk-Based Radioactive Acceptance Criteria of Municipal Solid Waste Landfill (MSWL, including municipal refuse landfills or industrial solid waste landfills, MSWL). At first, health risk assessment
  • Simulation of High-Sensitive Measurement for ~(239)Pu
  • According to the characteristic of low-energy transuranic element 239Pu in reprocessing plant site, an in vivo measurement experimental system with room temperature semiconductor detector array (CZT or Silicon detector) for 239Pu internal contamination is studied.
  • Neutron Ghost Imaging Technology Research on CARR Reactor
  • Ghost imaging is also known as quantum imaging. Different from the classical imaging, the neutron ghost imaging is based on the quantum mechanics properties of light field and its intrinsic parallel characteristic, and developed by new optical
  • Monte Carlo Simulation for Moderator of Compact D-T Neutron Generator
  • In order to study the neutron moderation of D-T neutron generator, moderators with diffident materials and structures are predicted by Monte Carlo simulations. Neutron generator is simplified as the diameter 20 cm, length 25 cm cylinder. The target is very
  • Mapping Nuclear Decay to Complex Network
  • Network model is always a key topic in the research of network science. Large Unifying Hybrid Network (LUHNM) theory, which we proposed before, is a universal network model that can be used to depict the diversity and complexity of the natural network.
  • Study of Associated α Particle Imaging Technique for Explosives Detection
  • The explosive detecting technique about neutron mainly include the thermal neutron analysis (TNA), the fast neutron analysis (FNA), the pulse fast and thermal neutron analysis (PFTNA) and the associated α particle imaging technique about fast neutron (API).
  • Monte Carlo Simulation of Dosimetric Parameters for HYBRID PdI Source in Brachytherapy
  • A novel brachytherapy source model, ADVANTAGE HYBRID PdI, has been designed by CIAE For treatment of cancer. In this project, the purpose of this study is to obtain the dosimetric parameters of HYBRID PdI source. The Monte Carlo simulation
  • NQR Stimulation Technique for Explosives Detection System
  • A method of customization stimulation signal based on direct digital frequency synthesis (DDS) for Nuclear Quadrapole Resonance Explosives Detection System is presented. DDS has many advantages, such as high frequency resolution, high convert speed,
  • Application of Grey Relational Cluster Method in Muon Tomography for Materials Detection
  • When the number of particles is small, We try to use grey system theory better in dealing the work which has little sample and incomplete information. Grey relational cluster method is applied for materials detection of the research of Muon tomography
  • Annual Report on SPR Operation in 2011
  • 1 Information of operation Operation person: present chief operators are 11 persons, operators are 6 persons; new chief operators are 3 persons, new operator is 1 person; training chief operators are 3 persons, training operators are 1 persons;
  • HI-13 Tandem Accelerator in 2011
  • In 2011, HI-13 tandem accelerator provided 27 kinds of ions and 3800 hours beam time. The distribution of beam time versus ion was shown in Fig. 1. The tank has been opened 6 times in 2011, most of problems caused by the laddertron charging
  • Operation and Service Based on 5SDH-2 Accelerator
  • The 5SDH-2 accelerator was imported from National Electrostatics Corporation of USA in 1996, which is mainly used to establish mono-energitic neutron reference field. The pulsed upgrading belonging to Key Laboratory project was finished including computer control system in 2006.
  • International Scientific Technology Exchanges in 2011
  • In 2012, CIAE sent 432 scholars abroad for taking part in international meeting, technical visiting, further studying and training. CIAE received more than 300 foreign scholars from about 30 countries, and some reports were given by foreign scholars as follows:
  • CIAE Seminars in 2011
  • Subject of Prize of Science, Technology and Industry for National Defense
  • Subject of Prize of Science & Technology for China National Nuclear Corporation
  • Subject of Prize of Science & Technology for China Nuclear Energy Association
  • National Prize for Progress in Science and Technology on Energy in 2010
  • Science and Technology Award of Beijing Municipality in 2010
  • CIAE Application of Patent in 2011
  • CIAE Patent in 2011
  • List of Scientific Publication in Foreign Languages in 2011
  • 1 Metrologia, Vol. 48, 2011 1) International key comparison of measurements of neutron source emission rate (1999-2005): CCRI(III)-K9. AmBe, technical supplement, 06018. Roberts N J (National Physical Laboratory), WANG
  • List of Scientific Publication in Chinese in 2011
  • 1 Acta Physica Sinica, Vol. 60, 2011 1) Influence of nucleon motion on the effective mass and energy of kaon in dense nuclear matter, No. 1, 012501. XING Yong-zhong(Department of Physics, Tianshui Normal University), et al
  • List of Lectures in International Meetings in 2011
  • Progress of China Experimental Fast Reactor in 2011
    Progress of Project “The Key Technology Research of Passive Shutdown System for CDFR”
    Summary of Research on Interactive Safety Analysis Program of Pool Type SFR
    PREFACE
    Application of INPRO Methodology in Evaluation of Nonproliferation Features of TWR
    Measurement and Analysis of Sodium Void Reactivity Effect in CEFR
    Thermal Fatigue Analysis of Takeover Pipeline
    Analysis of Design of Sodium Reception and Secondary Loop Sodium Plugging and Removal System for Fast Reactor
    coustic Leak Detection Based on Wavelet Packet and Genetic Algorithm for LM FBR Steam Generators
    Research on Valve Body Design of Large Bore Sodium Valve
    Analysis of Leak Before Break and Calculation Method of Critical Crack
    Manufacture of Simulator of Irradiation Device for China Experimental Fast Reactor
    Progress of Research on Demonstration Fast Reactor Main Pipe Material
    China Advanced Research Reactor Project Progress in 2011
    Progress Report of Beijing Radioactive Ion-Beam Facility (BRIF) in 2011
    Construction Progress of CYCIAE-100
    Completion of Main Magnet Fabrication for CYCIAE-100
    Progress of the Water Cooling System for CYCIAE-100
    Main Magnet Installation in the Temporary Building for CYCIAE-100
    Installation and Commissioning of the Main Magnet Elevating System for CYCIAE-100
    Installation of the Magnetic Mapping Device for CYCIAE-100
    Mapping and Shimming of Magnetic Field in CYCIAE-14
    Primary Design and Study of the Lattice Structure in Scaling FFAG
    Processing and Installation of the Stripping Probe for CYCIAE-100
    Mechanic Design of the Radial Probe Target for CYCIAE-100
    Calculation of New Beam Dump Shielding for CYCIAE-100
    Development of Pre-amplifier Module for BF_3 Counting Tube
    Design and Experimental Study of the External H~- Ion Source for a 10 MeV Medical Cyclotron
    Design of a Compact Pulsed Power Accelerator
    Design of Spiral Inflector and Central Region for a Medical Cyclotron
    Design of Main Elements of the Axial Injection Line for CYCIAE-100
    Peak Detector Circuit for DCCT Improvement(Antonino Amato)
    Manufacture of the RF Cavity for CYCIAE-100
    Mechanical Design of the Injection Beam Line of Small Medical Cyclotron
    Mechanical Design of the Inflector and Central Region of Small Medical Cyclotron
    Measurement and Simulation of Beam Centering on CYCIAE-10
    Simulation on the Pulsed Beam Transport for Injection Line of CYCIAE-10
    Insulation Consideration of the Cryo-vacuum System for CYCIAE-100
    Concept Design of Multipacting Measurement Circuit With Nano-second Resolution
    Mechanical Improvements on the Main Magnet for CYCIAE-14
    Progress of CRARL in 2011
    Progress on Radioactive Waste Treatment Facilities Construction
    Tensor Effect on Proton Bubble Structure of ~(46)Ar
    Shell Model Study on the Proton Pigmy Dipole Resonances in ~(17, 18)Ne
    Microscopic Effective Charges and B(E2) Values of Terminating States in Mirror Nuclei ~(51)Mn and ~(51)Fe
    Fusion Reactions of ~(16)O+~(76)Ge and ~(18)O+~(74)Ge Near Coulomb Barrier
    High-Spin States in ~(86)Sr
    High-Spin States in ~(87)Sr
    Fast Timing: Lifetime Measurements With LaBr_3 Scintillators
    Technique of Measuring Effective LET in Integrated Circuit (IC)
    Study on p+~(28)Si Reaction for Proton Single Event Effects Research
    Immunofluorescence Detection of γ-H2AX Foci Induced by ~7Li Ions and γ-rays Radiation
    Research of Fast Neutron Radiation Effect on Rats
    Test of RPC Detector by Cosmic Ray
    Calculation for Single Spin Asymmetry of Neutral Pion in Polarized Protons Collision at 200 GeV
    GEM Detector Electric Field Simulation
    Progress in Measuring ~(238)U(n, xnγ) Cross Sections With HPGe Detector Array
    Design of Pre-collimator System for Neutronics Benchmark Experiment
    Study of Fast Neutron Background Detection at Deep Underground Laboratory
    Calibration of Li-glass Detector Efficiency
    Lifetime Measurement of Inner Shell in the Collision of Fe, Au Ions and C Foil
    Phase Stability of Intermetallic Compound Ce_3Al in Mechanical Milling
    Renewal and Modified Evaluation Data of ~(233)U in CENDL_-3.1
    Uncertainty Analysis for Neutron Leakage Spectrum of LLNL Pulsed Sphere Facility due to Fission Cross Sections of ~(235)U
    Calculation of Prompt Fission Neutron Spectra for ~(235)U (n,f)
    Systematic Characteristics of Fast Neutron Fission Cross Sections for Actinide Nuclei
    Benchmarking ~(232)Th Evaluations With KBR and Thor Experiments
    Study on the Processing Method for Resonance Self-shielding Calculations
    Research on Nuclear Reaction Network Equation for Fission Product Nuclides
    Iso-spin Dependent Microscopic Optical Model Potential Based on Dirac Bruckner Haretree Fock Method
    Preparation of ~(64)Ni-Gd-Cu Target
    Preparation of Super-Thin, Large-Area, Double-Sided Gold-Plated Mylar Film
    Post Accelerator for Proposal of CARIF
    Reliability Test of an ECR Ion Source for Accelerator Driven Sub-critical System (ADS)
    Development of ECR Ion Source for ADS
    Installation and Trial Run of the Furnace
    Progress in Neutron Texture Diffractometer at CARR
    General Design for CARR Neutron Guide System
    Experimental Software Design of the Neutron Texture Diffractometer at China Advanced Research Reactor
    Floating Zone Growth of LiFePO_4 Single Crystals
    H_3~(10)BO_3/ZnS(Ag) Scintillator Screen for Thermal Neutron Radiography
    Non-destructive-Testing of Nuclear Fuel Element by Means of Neutron Imaging Technique
    Crystal Structure and Thermal Expansion Properties of Lu_(2-x)Fe_xMo_3O_(12)
    Neutron Time of Flight Spectrometer for Velocity Selector Calibration
    Progress Report of Small Angle Neutron Scattering on CARR
    Small Angle Neutron Scattering Study on Structure of PAMAM Dendrimer Encapsulation With Small Molecules in Aqueous Solution
    Investigation on Crystal Structure, Magnetism and Colossal Magnetoresistance of Y_2CrS_4
    Study on Different Forms of Calcium Metabolic Behavior in Normal and Osteoporosis Rats by ~(41)Ca Tracing
    Discussions of Chemical Extraction Methods for Iodine-129 Determinations Using AMS System
    Superheated Droplet Detector Response for Temperature
    Key Issue of Ultra-trace Environmental Samples by ~(236)U/~(238)U-AMS Method
    Suppression Factor of ~(182)W for ~(182)Hf AMS at CIAE
    Study on Different Samples in Measurement of Manganese-53 With AMS
    Design of Stopper of Prompt Gamma Neutron Activation Analysis Facility at China Advanced Research Reactor
    Preliminary Study on the Determination of ~(235)U and ~(239)Pu Using Delayed Neutron Counting Method
    Radiation Effect of CLAM Steel by Triple Ion Beams Irradiation
    Investigation of H-Pd, H-PdAg and H-PdY Alloy Systems by Positron Annihilation Lifetime Spectroscopy
    A SSS Spectrometer
    Construction Design of Tissue-Equivalent Proportional Counter
    Manufacture of Single ~(60)Co Source Irradiation Facility
    Recent Progress in Research on Microcalorimeter for Radioactivity Measurement of Tritium
    Recent Progress in Liquid Scintillation Counting System for Absolute Radioactivity Measurement
    Design of Radioactive Reference Barrels and Simulation Verification of Linear Source
    Study of Preparation of Large Area Standard Source
    Development of Nanosecond Short Pulse High Power KrF Laser System(SZATMAR Sador[1] BOHUS Janos[2])
    Experimental Study on Planarity of Shock Waves Driven by High Power Eximer Laser Pluses
    Energy Spectrum of Protons Driven by Ultra-short Laser Interaction With Thin Gold Foils
    Influence of Laser Prepulse in Ultra-short Laser-Driven Proton Acceleration
    Proton Acceleration Drived by High-intensity Ultraviolet Laser
    Plasma Expansions With Time-Dependent Electron Temperature
    Investigation of Isotope Separation Utilizing Spontaneous Magnetic Field of Ultra-Short Laser Pulses
    Calculation for Improvement of 350 keV Electron Accelerator
    Research of Elements for Beam Redistribution
    Dynamics Calculation of CH-DTL
    Dynamics Calculation of Spoke
    Dynamics Calculation of Travel Wave Tube
    Calculation of Uniform of Beam Scanning
    Design of Cavity for 10 MeV Electron Irradiation Accelerator
    Research of Quick-Response Protective System for Klystron of Multi-Energy Electron Linac
    UHV Vacuum System R&D of Multi-energy Electron LINAC
    Self Shielding System R&D of 350 keV High-Voltage Electron Accelerator
    Nuclear Fuel Solution System Transient Analysis
    Consultative Report on NPP Improving Loading Factor
    Study Report of Design Guide for Tube Arrays in Cross Flow
    Study Report of Design Guide for Single Circular Cylinder in Axial Flow
    Study Report of Design Guide for Single Circular Cylinder in Turbulent Cross Flow
    Numerical Model Analysis of Fluid-Elastic Instability of Thin Rectangular Plate Due to Overflow
    Small Punch Test on Before and Post Irradiated Domestic Reactor Pressure Steel
    Status of R&D on Tritium Permeation Barrier Coatings for Tritium Breeding Blanket of Fusion Reactor
    Failure analysis for JNK Boracic acid Tank Room of NPP
    Piping Stress Analysis of Secondary Cooling Water System in CARR
    Stress Assessment of Security Injection Tank
    Thermal Stress Analysis of Security Injection Tank
    Anchor Stress Checking of Security Injection Tank
    Static Stress Analysis of Security Injection Tank
    Seism Analysis of Security Injection Tank
    Buckling Analysis of Supporting Skirt of Security Injection Tank
    Radiation Measurement for Ji Nan MNSR Decommissioning
    Preliminary Design of Special Unloading Tool for Miniature Neutron Source Reactor
    DAQ System of Current Based on MNSR
    Preliminary Research of Neutron Energy Spectrum of Thermal Neutron Beam Port for IHNI
    Study on Anode Process in Molten Salt Electrolysis of CeO_2
    Concentration Determination of Tetravalent Uranium by Direct Spectrophotometric Method
    Determination of α Dose Rate of ~(238)Pu Solution
    Preparation of Uranous Nitrate by Membrane Electrolysis
    Research of Trend of Technetium in U/Pu Partition Step of APOR Process
    Extraction of Np(Ⅳ, Ⅴ, Ⅵ) Ions From Aqueous Nitric Acid Solutions With TODGA and DHOA
    Valance Adjustment of Np and Pu in 1AF Fluid of Pilot Plant
    Study on Extraction Performance of Tri-iso-amyl Phosphate
    Catalytic Reduction of U(Ⅳ) With Hydrazine in Nitric Acid Solutions
    Determination of Trace Plutonium in Uranium Product by ID-ICP-MS
    Determination of Micro U, Np, Pu by Highly Oriented Pyrolytic Graphite Pre-diffraction EDXRF
    Analytical Instrument of X-ray Fluorescence Determine Concentration of U and Pu in Organic Solution at the Same Time
    U(Ⅳ) Preparation by Method of Electrolysis
    Separation and Purification of Fissiogenic Ruthenium From Irradiated Uranium
    Development of an Analytical System for Determination of Free Acid via a Joint Method Combining Density and Conductivity Measurement
    Development of an Analytical System for Rapid, Remote Determining Concentration and Valence of Uranium and Plutonium
    Study of Multi Total Reflection X-ray Fluorescence Spectrometer
    Study Progress of On-line Monitoring Device for Uranium and Plutonium by XRF
    Study on Radiochemical Separation and Measurement of Half-life of ~(88)Kr
    A Method for Determination of ~(99)Tc in Soils Using TEVA Resin
    A Convenient Method for Synthesis of 2-allyloxymethyl-18-crown-6
    Determination of Stability constant of Coordination Reaction of 2-allyloxymethyl-18-crown-6 with Sr~(2+) in Water
    Study on Performance of Empore~(TM) Technetium Rad Disks
    Study on Performance of Empore~(TM) Strontium Rad Disks-Ⅱ
    Sequential Separation of U, Np and Pu From Environmental Samples
    Separation of Uranium From Spent Fuel Solution in Burnup Measurements Process
    Separation of Molybdenum From Spent Fuel Solution in Burnup Measurements Process
    Content of Transuranium Nuclide in Process of Irradiating Thorium
    Morphology Characterization of Uranium Particles From Laser Ablated Uranium Materials
    Studies on Measurement of Impurities in Uranium Sample
    Monitoring Fallout From Fukushima, Japan After Nuclear Accident
    Preparation of Inorganic Sorbent KNiFC and Its Application
    Preparation of Inorganic Sorbent for Strontium and Its Application
    Destruction of Tributyl Phosphate and Exchange Resin by Electrochemical Oxidation
    Site Cleanup of Radioactive Isotope Container Rinsing Pool and Surrounding Environment
    Biodistribution of ~(99)Tc~m Labelled Dextran Conjugates for Sentinel Lymph Node Detection
    Preparation, Radiolabelling and Biodistribution Study of ~(177)Lu-DTPA-G3
    Preparation and Biodistribution Evaluation in Mice of ~(177)Lu-DOTA-TOC
    Determining Contents of Five Impurities in Cyclotron- Produced ~(64)Cu Solution by Emission Spectroscopy
    Determination of Medronic Acid and Its Related Substances by Reversed-Phase High-Performance Liquid Chromatography
    Quantification of Kryptofix2.2.2 in ~(18)FDG by HPLC
    Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of Enrofloxacin
    Development of Up-Converting Phosphor Immunochromatography Test for Quantitative Detection of Sulfadiazin
    Specific Activity and Impurities in Irradiated Natural Nickel Target
    Determination of Two Columns Performance
    Synchronizability Analysis of Harmonious Unification Hybrid Preferential Model
    Algebraic Condition of Nonlinear Dynamical Network Synchronization
    Unified Hybrid Network Theoretical Model Trilogy
    Influence of Deterministic Attachments for Large Unifying Hybrid Network Model
    Influence of Random Attachments for Large Unifying Hybrid Network Model
    Uranium Enrichment Analysis With Electromechanical Cooled HPGe Detector
    Development of Uranium Works Reference Sample for NDA Measurement
    γ Ray Radioactivity Measurement of ~(88)Y and ~(22)Na Point Source
    Study on Application of Mobile Radiological Monitor
    Emission Data-Analysis of TGS Under Continual Scanning Mode
    Transmission Data-Analysis of TGS Under Continual Scanning Mode
    Nuclear Material Accountancy Assessment Technical Measures in Nuclear Centrifuge Enrichment Facility
    Study on Calibration of Device of Heterogeneous Matrix With Uranium inside
    Software Development of Measurement System Heterogeneous Uranous Drums
    Study on Automatic Control of Measurement System Heterogeneous Uranous Drums
    Physical Protection System Effectiveness Evaluation Project
    Application Research of Developed Drummed Nuclear Waste Neutron Counting System
    Development on New Style of Drummed Nuclear Waste Neutron Counting System
    Supervisory Monitoring of Workplace at CIAE in 2011
    The Biokinetic Model of Americium
    Research on Health Risk-Based Radioactive Acceptance Criteria of Municipal Solid Waste Landfill
    Simulation of High-Sensitive Measurement for ~(239)Pu
    Neutron Ghost Imaging Technology Research on CARR Reactor
    Monte Carlo Simulation for Moderator of Compact D-T Neutron Generator
    Mapping Nuclear Decay to Complex Network
    Study of Associated α Particle Imaging Technique for Explosives Detection
    Monte Carlo Simulation of Dosimetric Parameters for HYBRID PdI Source in Brachytherapy
    NQR Stimulation Technique for Explosives Detection System
    Application of Grey Relational Cluster Method in Muon Tomography for Materials Detection
    Annual Report on SPR Operation in 2011
    HI-13 Tandem Accelerator in 2011
    Operation and Service Based on 5SDH-2 Accelerator
    International Scientific Technology Exchanges in 2011
    CIAE Seminars in 2011
    Subject of Prize of Science, Technology and Industry for National Defense
    Subject of Prize of Science & Technology for China National Nuclear Corporation
    Subject of Prize of Science & Technology for China Nuclear Energy Association
    National Prize for Progress in Science and Technology on Energy in 2010
    Science and Technology Award of Beijing Municipality in 2010
    CIAE Application of Patent in 2011
    CIAE Patent in 2011
    List of Scientific Publication in Foreign Languages in 2011
    List of Scientific Publication in Chinese in 2011
    List of Lectures in International Meetings in 2011
    《中国原子能科学研究院年报:英文版》封面
      2011年
    • 01
      2008年
    • 01
      2007年
    • 01
      2006年
    • 01
      2005年
    • 01
      2004年
    • 01
      2003年
    • 01

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