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
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.
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.
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
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,
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,
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,
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,
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
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.
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
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
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
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.
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.
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
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,
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.
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
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.
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,
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,
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
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.
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,
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,
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
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
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,
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
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
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
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
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,
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.
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,
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
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.
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
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
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,
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
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
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
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
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,
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.
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.
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
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
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
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,
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
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,
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 (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
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
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
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
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
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
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.
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
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
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
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,
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.
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.
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
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
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
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
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
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,
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%.
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
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.
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.
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
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
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
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
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,
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
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
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
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
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
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 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
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 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
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
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,
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
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
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
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
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.
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
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,
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
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.
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
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
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.
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 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
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)
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
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)
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,
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,
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,
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
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
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:
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.
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,
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.
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
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
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.
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
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
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
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
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
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
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.
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
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
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.
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.
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
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.
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
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.
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,
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
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
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,
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
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:
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%.
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
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
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
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 ),
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
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
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.
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) 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
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.
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
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
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.
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,
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,
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,
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
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
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.
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
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
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
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,
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,
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
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
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
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
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,
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
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.
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,
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
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
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.
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
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
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
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
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,
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
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,
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.
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,
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
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,
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.
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
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;
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,
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
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
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.
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
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.
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
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
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
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
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.
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
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
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.
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).
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
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,
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
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;
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
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.
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:
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
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