最新刊期
      卷 41 ， 期 7 ， 2018

        LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS

      • Lei LI,Jianmin SHI,Na YANG,Yuanlong PANG,Xuqiang LIU,Guang ZENG,Guixia YANG
        Vol. 41, Issue 7, Article number: 070201(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070201
        摘要：BackgroundHeavy metal process is widely used to improve the reliability of electronic devices, which introduces interface formed by high Z and low Z material. There will be dose enhancement effect within region near such interface when exposing to low energy γ-ray field. This phenomenon could affect the reliability of hardness assurance tests. PurposeA method was introduced to evaluate the proportion of low energy scattering γ-ray within high dose rate irradiation field formed by cobalt source. MethodsTwo types of ionization chambers were designed, which utilize single layer Al(aluminum) wall and double layers Au(gold)/Al wall respectively. The γ-ray induced current of the latter ionization chamber varied more rapidly with the change of γ-ray energy than the former one. Consequently, the ratio of those two currents was sensitive to γ-ray energy, and the variation between measured and reference value of ratio could indicate whether the proportion of low energy γ-ray was over expectation obviously. ResultsIt was advised that the reference value could be set as 2.8 based on analysis of typical energy spectrums of cobalt source. In addition, an ionization chamber dosimeter system with the range of 0.01~2.3Gy·s-1(Si) was designed with which the ratios were measured in free field and Pb(lead)/Al box reducing the amount of low energy γ-ray. There was an agreement between experimental and calculated results. ConclusionThe method is effective for evaluating the proportion of scattering γ-ray and the effectiveness of spectral hardening technology. Furthermore, it could help correlate different irradiation fields or irradiation positions within specific irradiation field from the aspect of irradiation dose.  
        关键词：Dose enhancement effect;Cobalt-60 source high dose rate field;Low energy scattering γ;Evaluation method;Plane-parallel ionization chamber   
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        发布时间：2021-05-19

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • Yipeng PENG,Chenggang YU,Deyang CUI,Shaopeng XIA,Fan ZHU,Xiangzhou CAI,Jingen CHEN
        Vol. 41, Issue 7, Article number: 070602(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070602
        摘要：BackgroundCompared with the molten fluoride salt reactor, the molten chloride salt fast reactor (MCFR) has outstanding advantages in terms of transuranics (TRU) solubility, neutron spectrum and melting point, so it is very crucial to study neutron performances of the MCFR to evaluate its feasibility. PurposeThis study aims to optimize the composition and reprocessing method of the molten salt to enhance the breeding and burnup performance of MCFR. MethodsBased on the molten salt reactor reprocessing sequence (MSR-RS), the effect of different carrier salt and starting fuel on burnup performance are analyzed and the composition of molten salt is optimized. Then, off-line batch reprocessing and on-line continuous reprocessing are introduced to improve burnup performance. ResultsAfter a series of optimization, the burnup-time is extended to 31 a, the burnup level is increased to 210GW·d·t-1, the production of 233U is 8300 kg, and finally 12000 kg of TRU is consumed corresponding to transmutation rate of 62.1%. ConclusionNaCl is a more suitable carrier salt for MCFR, and minor actinides (MA) in the TRU also helps to improve the breeding performance. Batch reprocessing can not only achieve great burnup performance but also reduces the requirement for the reprocessing system.  
        关键词：MCFR;Thorium uranium fuel cycle;Burnup   
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        发布时间：2021-05-19
      • Yue HE,Maosong CHENG,Zhimin DAI
        Vol. 41, Issue 7, Article number: 070603(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070603
        摘要：BackgroundTraditional nuclear energy simulation systems generally adopt the distributed service deployment based on the physical machines, there exist problems such as low resource utilization, difficulty in deployment and expansion. PurposeThis study aims to design and implement cloud simulation platform for thorium-based molten salt reactor (TMSR) by making use of cloud computing platform's advantages of flexible resource scheduling, agile operation and etc. MethodsCombining these advantages of cloud computing platform, a hierarchical and modular system architecture of TMSR cloud simulation platform was deployed. Then, a TMSR cloud simulation test platform was built to verify the technical feasibility of building the TMSR cloud simulation platform based on OpenStack. The functional modules of thorium-based molten salt experimental reactor-solid fuel (TMSR-SF1) engineering simulator were migrated to the TMSR cloud simulation test platform, which implements service deployment based on cloud computing. ResultsUsers can access TMSR-SF1 simulation services through the browser without installing any client software. At the same time, the simulation resources provided by the platform are modular, and each module can be used independently or in combination. ConclusionAfter running tests, the TMSR cloud simulation test platform can provide users with the required TMSR-SF1 simulation resources quickly and efficiently throughout the software lifecycle, enabling rapid and flexible deployment and reconstruction of simulation systems.  
        关键词：TMSR;Cloud simulation platform;System architecture;OpenStack;Engineering simulator   
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        发布时间：2021-05-19
      • Xuanxuan BI,Guangyao SUN,Lijuan HAO,Jing SONG,Liqin HU
        Vol. 41, Issue 7, Article number: 070604(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070604
        摘要：BackgroundCritical boron concentration search is considered as an important part of reactor design and analysis, but traditional search method requires multiple criticality calculations, hence low efficiency. PurposeIn order to overcome the disadvantages of the traditional search method, a highly efficient Monte Carlo critical boron concentration search method is developed and verified. MethodsFirst of all, the critical boron concentration search is treated as a perturbation problem. Then the adjoint flux method is adopted for perturbation calculation whilst the adjoint flux is calculated by the iterated fission probability method in the Monte Carlo simulation. The adjoint flux and the effective multiplication factor on the boron concentration response coefficients of the initial state can be obtained by only one criticality calculation, and the critical boron concentration is directly derived from the response coefficients. Finally verification is made on the standard Westinghouse 17×17 assembly model. ResultsThe numerical results of verification show a good agreement with reference results. ConclusionThis method can be effectively applied to critical boron concentration search.  
        关键词：Criticality search;Adjoint flux;Iterated fission probability;Perturbation;SuperMC   
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        发布时间：2021-05-19
      • Jun YAO,Bin CHEN,Shouhua JIAO,Xiang CHAI,Yanhua YANG
        Vol. 41, Issue 7, Article number: 070601(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070601
        摘要：BackgroundIn the design of some small modular reactor (SMR), the upper head of containment vessel is immersed in a large amount of coolant. After a severe accident, the residual heat inside containment vessel is then removed by natural convection above the upper head. PurposeThis study aims to undertake research into the two-dimensional natural convective heat transfer above the upper head of containment vessel and the flow field around it. MethodsA rectangular enclosure device with bottom curved heating surface was utilized to perform experiments under normal pressure. Particle image velocimetry (PIV) technique was employed to measure flow field. ResultsThe average Nu number, local heat transfer intensity, velocity field due to curved heating surface were obtained and analyzed. ConclusionThe average Nu number rises as heating power increases, while the growth rate has a descending trend. Along curved heating surface, local heat transfer intensity decreases first and then increases, lowest value of which occurs near 40° position of curved heating surface. Flow field around curved heating surface is visually revealed. Flow stratification becomes obvious near bulk flow, and the trend afterX=50 mm is reverse. Stratification is mainly due to the horizontal component of velocity. The maximum velocity is irrelevant to heating power, whose major influence lies upon the velocity of bulk flow and its horizontal component.  
        关键词：Rectangular enclosure;Natural convection;Curved heating surface;PIV   
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        发布时间：2021-05-19
      • Hui TANG,Zhoutong HE,Can ZHANG,Xue WANG,Huihao XIA
        Vol. 41, Issue 7, Article number: 070605(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070605
        摘要：BackgroundThorium molten salt reactor (TMSR) is a nuclear fission reactor using nuclear graphite as neutron reflector and moderator and molten 2LiF-BeF2 (FLiBe) salt as primary coolant. In TMSR, graphite is directly in contact with the molten salt. Given the porous nature of graphite, molten salt may penetrate into its pores in molten salt reactor environments, which may change graphite's thermal and mechanical properties. PurposeThis study aims to verify whether the FLiBe salt penetrates into candidate nuclear graphite and to test the amount of infiltrated molten salt, which is of vital importance to the safety in operation of the reactor. MethodsAn equipment used for static infiltration tests was developed to investigate the infiltration rate of molten FLiBe salt into graphite materials under different pressures. Effects of temperature and duration on the molten salt infiltration behaviors of graphite materials were also studied. ResultsThe threshold pressure for FLiBe salt infiltration for TMSR candidate graphite T220 was between 600 kPa and 700 kPa at 700℃. The higher the infiltration pressure, the greater the infiltration rate, while the increase amplitude decreased gradually. The infiltration rate of three grades of graphite after infiltration tests in different temperatures (600℃ and 700℃) and durations (20~2000 h) showed no significant difference. ConclusionFLiBe salt could not penetrate into graphite T220 in TMSR environments (< 500 kPa). Both factors of temperature and duration had little effects on infiltration behaviors of graphite materials.  
        关键词：TMSR;Nuclear graphite;Equipment used for infiltration test;Infiltration rate   
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        发布时间：2021-05-19

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • Xianfang MENG,Yin YIN,Long ZHANG,Ke CAO,Huiling MA,Shijun WANG,Peizhong QIN
        Vol. 41, Issue 7, Article number: 070401(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070401
        摘要：BackgroundEnvironment gaseous radioactive iodine monitoring is important for nuclear power plant safety. 131I detection efficiency is an important parameter for environment gaseous radioactive 131I monitoring equipment. PurposeThe aim is to explore an easy and simple approach which can estimate 131I detecting efficiency in iodine sampling cartridge based on 133Ba source. 133Ba has γ rays of similar energy characteristics as 131I and has long half-life. MethodsAccording to some iodine detector sampling and detecting device, some work have been carried out including experiments and detection efficiency estimation and simulated calculation with SuperMC program under conditions similar to experiment. ResultsDetection efficiency experimental estimation results consistent with Monte Carlo (MC) simulation results within 6.0%. ConclusionThe study suggests that the simple experimental method can be used to estimate the iodine sampling cartridge 131I detection efficiency.  
        关键词：131I sampling cartridge;Detecting efficiency;133Ba point source;SuperMC program   
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        发布时间：2021-05-19
      • Longwei LAI,Yongbin LENG,Yingbing YAN,Fangzhou CHEN,Jian CHEN,Weimin ZHOU,Ning ZHANG
        Vol. 41, Issue 7, Article number: 070402(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070402
        摘要：BackgroundData acquisition and signal processing of stripline beam position monitor (SBPM) and cavity beam position monitor (CBPM) is important for the high resolution beam control on free electron laser (FEL). The resolution requirements of SBPM and CBPM are 10 μm and 1 μm respectively at the beam current of 0.5 nC on Dalian coherent light source (DCLS) and Shanghai X-ray free electron laser (SXFEL). PurposeThis study aims to develop a digital BPM processor (DBPM) to meet those requirements and apply to both DCLS and SXFEL. MethodsThe DBPM is designed as a standalone instrument which includes radio frequency (RF) signal conditioning, analog signal digitizer, digital signal processing, and system controller. A field programmable gate array (FPGA) chip is used as system central component, and the experimental physics and Instrument control system (EPICS) is integrated in the advanced RISC machine (ARM) Linux for data acquisition and communication. Both the Lab test and practical on-site test for DCLS are performed. ResultsBeam test results of DBPM resolution on SBPM and CBPM are 4 μm and 0.4 μm, respectively. ConclusionThe DBPM performance meets the design specification and has been applied on DCLS successfully, it will be applied to SXFEL.  
        关键词：FEL;DBPM;SBPM;CBPM;DCLS;SXFEL   
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        发布时间：2021-05-19

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • Chunyu XIE,Hanjie CAO,Zenghui YUE,Hongliang BAO,Jianqiang WANG
        Vol. 41, Issue 7, Article number: 070102(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070102
        摘要：BackgroundThorium-uranium mixed oxides exist in different stages of the thorium fuel cycle. The physicochemical properties of Th-U mixed oxides, such as melting point, solubility, and oxido-reduction, are closely related to their microstructures. PurposeThis study aims to study the microstructure of the Th-U mixed oxides by X-ray absorption fine structure (XAFS) technique. In order to macroscopically simulate the physical and chemical properties of Th-U mixed oxides, relevant microstructure data are provided. MethodsThe local structures of Th and U in as-prepared Th1-xUxO2+y samples are obtained by XAFS spectroscopy technique. ResultsThe Th and U L3-edge XAFS data shows that the dominant structure in Th1-xUxO2+y is the mixture of ThO2 component and local U3O8 component. The extended X-ray adsorption fine structure (EXAFS) data of Th0.8U0.2O2+y sample is further analyzed. The result shows that there is Th-U interaction in Th0.8U0.2O2+y sample. The Th-U interaction results that the Th-Th/U bond length in Th0.8U0.2O2+y slight shorter than that of pure ThO2 and the U-O bond length in Th0.8U0.2O2+y larger than that of pure U3O8. ConclusionThe XAFS technique can supply complementary structure information of Th-U mixed oxides, such as the local structure of Th and U.  
        关键词：Synchrotron radiation;XAFS;Th-U mixed oxides;Microstructure   
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        发布时间：2021-05-19
      • Limin JIN,Li SONG,Wanqian ZHU,Hongxin LUO,Zhongmin XU,Zengyan ZHANG
        Vol. 41, Issue 7, Article number: 070101(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070101
        摘要：BackgroundSilicon crystal is one of the key optical materials in synchrotron radiation beam line. It is mainly used in double-crystal monochromator. Its main function is to separate the single-wavelength beam for the specific analytical experiments. Therefore, the processing quality of the crystal has an important impact on the synchrotron radiation quality, and the quality inspection on the beam-receiving surface of the crystal is also particularly important. The current conventional method is mainly to use optical microscopy and scanning electron microscopy (SEM) to detect the surface quality of the crystal, then discover the invisible micro-cracks, protrusions, scratches, grooves or other type of damage. PurposeThe aim is to introduce and propose a simple and feasible detection & characterization approach based on optical interference method. MethodsWith the experimental methods, to detect and characterize the above-mentioned damage on the silicon crystal surface by using Fizeau laser interferometer and atomic force microscopy (AFM). By determining the specific location of the micro-damage and quantitatively characterizing its size (length, width, height/depth, etc.), the possible impacts of the micro-damage on the optical performance of the crystal is evaluated. ResultsThe surface morphology of the tested crystal has been detected using Fizeau laser interferometer, and the interference pattern has been obtained. For the surface with micro-damage, an obvious abnormal structure is found to distinguish the location of the micro-damage. It is found as a slight bulge-type injury. The size parameters (width, height) are measured by AFM and compared with the lattice constant respectively. It is found that the former is much larger than the latter, therefore, the re-polishing process is necessary for the crystal. ConclusionAn effective and feasible method for quality detection and characterization of silicon crystal surface has been proposed.  
        关键词：Synchrotron radiation;Silicon crystal;Micro-damage;Optical interference method   
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        发布时间：2021-05-19

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • Bo WEI,Zhengjun ZHANG,Chuchu TONG,Jingen CHEN,Jifeng HU
        Vol. 41, Issue 7, Article number: 070502(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070502
        摘要：BackgroundAs one of the fourth generation of nuclear energy system, thorium molten salt reactor nuclear energy system (TMSR) has been greatly improved in sustainability, safety, economy and reliability. In the design and manufacture of TMSR, a large number of nuclear reaction data is indispensable. PurposeThe full set of microcosmic data for n+74, 75, 77, 79As reaction, including the theoretical calculations of total cross section, elastic cross section, various of reaction channels cross section, elastic and inelastic scattering angular distribution, energy spectra and double differential cross sections for six kinds of emitted particles (n, p, α, d, t, He-3), would be calculated. MethodsBased on the assumption of the optical model and the experimental data of total cross section and elastic scattering angular distributions for n+75As reaction, a set of optimal optical potential parameters which universally suitable for n+74, 75, 77, 79As are obtained. On the premise of the parameters, the cross sections, energy spectra and double differential cross sections for n+74, 75, 77, 79As reaction are calculated and analyzed by the UNF program which based on the optical model, distorted wave Bom approximation theory, the unified Hauser-Feshbach theory and exciton model. ResultsThe theoretical results of the full set of microcosmic data are in agreement with the experimental data, and the theoretical results of regions without experimental data are given. ConclusionThe full set of microcosmic data for n+74, 75, 77, 79As reaction based on this set of optical potential parameters is reasonable, the main theoretical model can describe the nuclear reaction commendably, the full set of microcosmic data obtained in this work can meet the requirements of nuclear engineering and medicine, it also has significance for the study of nuclear reaction.  
        关键词：The full set of microcosmic data for neutron nuclear reaction;Optical model;Reaction cross section;Hauser-Feshbach statistical theory and exciton model   
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        发布时间：2021-05-19
      • Wei HUANG,Cheng QIAN,Liangting SUN,Xuezhen ZHANG,Yun CAO,Wang LU,Yucheng FENG,Junwei GUO,Xing FANG,Xixia LI,Hongwei ZHAO
        Vol. 41, Issue 7, Article number: 070501(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070501
        摘要：BackgroundThe methods to produce metallic ions in high charge state electron cyclotron resonance (ECR) ion source are micro-oven method, sputtering method and metallic ion from volatile compounds (MIVOC) method and so on, amongst which the micro-oven method can help produce high intensity and high reliability ion beams. There are mainly two types of micro-oven in use, i.e. low temperature oven and high temperature oven. PurposeHigh temperature oven is especially used for metals with melting temperature over 1500℃, such as cobalt, titanium, vanadium, platinum, uranium, etc. MethodsUsing ANSYS, simulation and analysis of the temperature distribution on a tantalum crucible of high temperature oven, its thermal stress at high temperature and Ampere's force under the strong ECR ion source magnetic field working condition have been performed. ResultsAccording to the test, the deformation of tantalum crucible over 1800℃ after off-line test is consistent with the simulation in the ANSYS well, which puts forward an improved scheme. And the improved resistor heating micro-oven can remain stable at 1500℃ for 48 h and 1846℃ for 6 h in the off-line test. ConclusionThe designed resistor heating micro-oven can be used in ECR ion source for the production of high intensity highly charged refractory metallic ion beams.  
        关键词：ECR ion source;Resister heating;High temperature oven;Metallic ions   
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        发布时间：2021-05-19

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • Hong ZHANG,Yangchun LENG,Yanhui WANG,Jian LIU,Xianguo TUO
        Vol. 41, Issue 7, Article number: 070302(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070302
        摘要：BackgroundThe research on the disposal of clay rock in high-level waste is still in the initial stage, furthermore the research on the migration mechanism of nuclide in clay rock treatment system is weak. PurposeThis study aims at the adsorption behavior of U(Ⅵ) onto kaolin, and provides reference for the safety evaluation system of high level waste disposal storehouse. MethodsThe effects of initial concentration of U(Ⅵ), pH and coexisting ions on the adsorption of U(Ⅵ) onto kaolin are investigated at the temperatures of 298.15 K, 308.15 K, 318.15 K and 328.15 K. ResultsThe results show that the adsorption of U(Ⅵ) onto kaolin is increasing with the increase of initial concentration of U(Ⅵ). At the same concentration of U(Ⅵ), the adsorption of U(Ⅵ) onto kaolin is increasing with the increase of temperature. When the pH was 7, the adsorption of U (Ⅵ) onto kaolin is best. At the same pH, the adsorption of U(Ⅵ) onto kaolin is increasing with the increase of temperature. The coexistent ions Ca2+, CO32- and SO42- have a greater inhibitory effect on the adsorption, at the same time the adsorption of U(Ⅵ) onto kaolin is increasing with the increase of temperature. Conclusionwith the increase of temperature, the adsorption capacity of kaolin on U(Ⅵ) is enhanced. The adsorption thermodynamic analysis proves that the adsorption of U(Ⅵ) onto kaolin is a spontaneous endothermic process. Through comparison of fourier transform infrared spectrometer (FT-IR), it is found that the absorption peaks have shifted and the intensity changes and appears a new peak, which proves that the adsorption of U(Ⅵ) onto kaolin is not only physical adsorption, there is also chemical adsorption.  
        关键词：U (Ⅵ);Kaolin;Temperature;Adsorption thermodynamics   
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      • Wanqiang ZHOU,Jingcheng JIANG,Jiangang HE,Xiangyun WANG,Liang DU,Xiaoli WANG,Zhaoyi TAN,Chunli LIU
        Vol. 41, Issue 7, Article number: 070301(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.070301
        摘要：BackgroundThe disposal of high-level radioactive wastes is critical for sustainable development of nuclear energy. And the adsorption, diffusion and migration behaviors of radionuclides in the environment depend on the chemical species in the system. PurposeThe paper aims to understand the speciation distribution of uranium and adsorption behavior on quartz and hydrous ferric oxide. MethodsThe speciation distribution and sorption of uranium are calculated by chemical speciation analysis software CHEMSPEC, which is developed by Peking University Nuclear Environmental Group. Results and ConclusionsThe calculation results indicate that uranium exists as UO2(CO3)34- and UO2(CO3)22- in the Beishan groundwater. And under acidic conditions, uranium mainly exists as U(OH)4(aq). While in neutral or weak alkaline conditions, the main species are UO2(CO3)22- and UO2(CO3)34-. When the solution is in strong alkaline conditions, most of uranium exists as UO2(OH)3-. And U(Ⅳ) is stable in the redox condition, while U(Ⅵ) is stable in the oxide condition. The concentration of different ions also has influence on the speciation distribution of uranium, and in the order of HCO-3 > F- > SO 42- > Cl -. With the increasing number of pH, the sorption extent of U(Ⅵ) on quartz is lager. And the maximum adsorption is at pH=4.3. When it comes to U(Ⅵ) sorption on hydrous iron oxide, the greatest sorption is at pH=5.7~8.2.  
        关键词：Uranium;CHEMSPEC;Speciation distribution;Sorption   
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