最新刊期
      卷 45 ， 期 1 ， 2022

        INVITED REVIEW

      • “在核能与空间技术领域，SiC MOSFET器件的单粒子效应问题日益突出。专家系统总结了国内外研究进展，为深入认识该问题提供参考。”
        LIU Cuicui,GUO Gang,LI Zhiming,ZHANG Fuqiang,CHEN Qiming,HAN Jinhua,YANG Xinyu
        Vol. 45, Issue 1, Article number: 010001(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010001
        摘要：With the rapid development of nuclear energy and space technology, application of high-voltage power devices based on SiC, especially the SiC MOSFET, is increasing. The problems of single event effect (SEE) caused by high-energy particle radiation in the radiation environment, such as, single event burnout (SEB) and single event gate rupture (SEGR), are becoming more and more prominent. In order to systematically understand the research progress of SiC MOSFET SEE, and accelerate the research of SiC MOSFET SEE mechanism and its radiation hardening technologies, the advantages of SiC MOSFET and the key problems in its radiation application are first demonstrated. Then, the simulation calculation, irradiation experiment and corresponding research results of SiC MOSFET SEE at home and abroad are comprehensively reviewed, and the main focus of related research is summarized. In addition, the possible reasons for the high sensitivity of SiC MOSFET to SEE is analyzed. Finally, possible future research directions of SiC MOSFET SEE are discussed according to current existing problems in this field. By systematically summarizing the research progress of SiC MOSFET SEE worldwide, it is expected to provide valuable reference for fully revealing the physical mechanism of SiC MOSFET SEE, and even further improving the radiation hardening technologies of SiC MOSFET to prevent the problem from SEE.  
        关键词：SiC MOSFET;Single event effect;Radiation hardening;Performance evaluation   
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        发布时间：2024-10-25
      • “辐照技术在冷冻肉类食品加工领域的应用，为新冠病毒消杀工艺制定提供参考。”
        DONG Juancong,CHENG Jiao,DANG Xuhong,WANG Chao,LIU Xiaoming
        Vol. 45, Issue 1, Article number: 010002(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010002
        摘要：Irradiation technology has been widely used in the field of food processing. It is urgent to figure out whether the quality of frozen meat food would change after irradiation, when the SARS-CoV-2 was detected in the imported cold-chain meat. The effects of irradiation on the quality of frozen meat are summarized from the aspects of food sensory, protein decomposition, fat oxidation, vitamin content and so on, providing reference for the formulation of irradiation for the elimination of SARS-CoV-2 and other viruses on frozen food, as well as the study of irradiated frozen meat and the industrial development of irradiated frozen food.  
        关键词：Ionizing radiation;Frozen food;Quality;Dose   
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        发布时间：2024-10-25

        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • “在硬X射线自由电子激光装置项目中，通过SOLID EDGE软件和ANSYS Workbench对1.3 GHz超导加速模组进行模型简化和振动分析，验证了有限元模型的准确性，为支撑方式选择和优化提供参考。”
        ZHEN Tingting,DENG Rongbing,GAO Fei,LEI Zhidi,YIN Lixin
        Vol. 45, Issue 1, Article number: 010201(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010201
        摘要：BackgroundThe superconducting cryomodule used in Shanghai high repetition rate X-ray freedom-electron laser (XFEL) and extreme light facility (SHINE) requires strict control of the position jitter tolerance which generally does not exceed 10% of the beam size. The root mean square values of the cavities' transverse displacement in the cryomodule should not exceed 300 nm between 1 Hz and 100 Hz.PurposeThis study aims to obtain the random vibration responses of the cryomodule with different length of screw rods hanging at the ceiling through finite element analysis (FEA) and vibration test, to judge whether the stability requirement is met, and to provide a reference for the selection and optimization of the support structure.MethodsFirst of all, simplified model of the cryomodule was constructed by SOLID EDGE, and the ANSYS Workbench was employed for modal analysis to obtain the natural frequencies and vibration mode of the structure. Then, random responses of the cryomodule hanging at the ceiling were carried out through FEA and vibration measurement. The root mean square values of cavities' transverse vibration in 1 Hz ~ 100 Hz frequency band got by simulation and measurement were compared to determine the accuracy of the model and the stability of the cryomodule. Finally, the vibration data of the cryomodule's further operating environment was monitored to confirm the stability of the structure.ResultsThe simulation and measurement results are in good agreement, the screw elongation of 8 cm has no effect on the vibration responses of the cavities.ConclusionThe accuracy of the model simplification proposed in this study is verified by FEA simulation and on-site measurement. The root mean square values of the cavities' vibration measurement meet the stability requirement for 1.3 GHz superconducting accelerator.  
        关键词：Superconducting cryomodule;Random vibration responses;Finite element analysis;Vibration test   
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        发布时间：2024-10-25
      • “在癌症治疗领域，专家设计了新型束流整形组件，优化了氘氚中子源在硼中子俘获治疗中的应用，为癌症治疗提供新方案。”
        ZHU Yinan,LIN Zuokang,LU Linyuan,YU Haiyan,CHEN Jingen,XIE Leidong
        Vol. 45, Issue 1, Article number: 010202(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010202
        摘要：BackgroundBoron neutron capture therapy (BNCT) is a promising treatment for cancer. In recent years, D-T neutron source has shown great potential as a suitable neutron source for BNCT. However, the neutron energy produced by a D-T neutron source is 14.1 MeV, which cannot be straightforwardly used in a BNCT, so beam shaping is necessary.PurposeThis study aims to design beam shaping assembly (BSA) to make the neutron beam of D-T neutron source suitable for BNCT.MethodsThe Monte Carlo simulation program MCNP5 was employed to design the corresponding BSA for D-T neutron source. The advantages of using natural uranium as neutron multiplicative layer was firstly verified by simulation. Then, the moderating layer was simulated together the supplementary moderating layer, reflective layer, shielding layer and thermal neutron absorption layer using different materials and thickness to obtain optimal configuration of these materials.ResultsSimulation results show that an ideal therapeutic neutron beam is obtained by using a 14 cm radius natural uranium as neutron multiplicative, 50 cm thick BiF3 and 10 cm thick TiF3 as a double-moderating layer, a 17 cm thick AlF3 as a supplementary moderator, a 0.2 mm thick Cd as a thermal neutron absorbing layer, a 3.5 cm thick Pb as a γ shielding layer and a 10 cm thick Pb as a reflecting layer. Combination of these materials is suggested to optimize and design as the neutron BSA.ConclusionsThe air outlet parameters of output neutron beam using BSA designed in this study can well meet the recommended values of the International Atomic Energy Agency (IAEA).  
        关键词：Boron neutron capture therapy;D-T neutron source;Monte Carlo simulation;Beam shaping assembly   
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      • “在辐射敏感晶体管领域，专家通过对比辐照试验，揭示了质子与60Co γ辐射响应差异的微观机理，为空间应用提供解决方案。”
        MA Han,SUN Jing,HE Chengfa,XUN Mingzhu
        Vol. 45, Issue 1, Article number: 010203(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010203
        摘要：BackgroundRadiation sensitive field-effect transistors (RADFETs) are calibrated on the ground using a 60Co γ-ray source that is different from the proton-electron radiation environment that exists in actual space applications.PurposeThis study aims to explore the influence of space protons on the radiation response of RADFETs.MethodsFirst of all, the comparative and combinative radiation experiments with 10 MeV proton and 60Co γ radiation were carried out. Then, the oxide-trap charge and interface-trap charge were separated by mid-gap technique (MGT) and charge pump (CP) method, and the generation process of proton primary knock-on atom (PKA) in oxide was simulated by Geant4 toolkit. Finally, the microscopic mechanism of RADFETs radiation response difference between proton and 60Co γ was investigated.ResultsThe results show that dose response of RADFETs to proton is insensitive in comparison with γ-ray, proton irradiation introduces certain displacement damage in RADFETs which will intensify the influence of trap charge near the interface on the measurement results.ConclusionsIt is necessary to use the proton and electron flux model to modify the measured data or carry out a specific calibration scheme for the RADFETs applied to space.  
        关键词：RADFETs;Proton radiation;γ radiation;Separation of traps charge   
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        发布时间：2024-10-25

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • “核医学SPECT/CT技术结合功能成像与结构解剖，广泛应用于疾病诊治，上海市制定报告规范，提高诊疗准确性。”
        SHAN Fengling,ZHANG Jinming,LIU Congjin,SHI Keqing,LIU Xingdang
        Vol. 45, Issue 1, Article number: 010301(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010301
        摘要：Nuclear medicine single photon emission computed tomography (SPECT) is a widely installed and used equipment in nuclear medicine department, which can reflect the changes of physiological, biochemical, functional and metabolic in vivo. SPECT has diverse tracers but lower special resolving power, while X-ray computed tomography (CT) has high resolution of tissue morphology. SPECT/CT combines functional imaging with structural anatomy, hence is widely used in the diagnosis and treatment of various diseases with high sensitivity and specificity. It has become a clinically recognized routine examination item and provides important information for clinical diagnosis and treatment. With the popularization of SPECT in hospitals at all levels in Shanghai, a standardized reporting format is needed. In order to provide high quality SPECT reports and provide a basis for clinical work, scientific research and teaching, standard elemental specification for SPECT imaging report was proposed to meet the mutual recognition of image report as required by National Health Commission of the People's Republic of China. According to the international guidelines and previous experience, the expert committee of Shanghai nuclear medicine quality control center has formulated the elements and specifications of SPECT imaging report in Shanghai, which provides a reference standard for SPECT imaging report.  
        关键词：SPECT;Reporting;Elements;Specification   
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      • “金属-有机骨架材料在乏燃料后处理废气中放射性氙和氪的吸附分离领域取得新进展，有望替代低温精馏法实现低成本分离。”
        CHEN Bin,WU Shan,SONG Xiaojing,MA Heping
        Vol. 45, Issue 1, Article number: 010302(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010302
        摘要：BackgroundThe adsorption and separation of Xenon (Xe) / Krypton (Kr) has received increasing attention due to the concern of reprocessing radioactive isotopes of Xe and Kr from off-gas of used nuclear fuel as well as the commercial value of high purity Xe gas. At present, the separation of Xe/Kr is mainly through cryogenic distillation, which is energy and capital intensive. Porous materials such as metal-organic frameworks (MOFs) have shown the ability to selectively adsorb xenon and krypton at relative high temperature, hence are expected to replace cryogenic distillation to achieve low-cost Xe/Kr separation.PurposeThis study aims to investigate the gamma radiation stability of three MOFs (Co/DOBDC, Ni/DOBDC, Co3(HCOO)6) used for Xe and Kr adsorption separation.MethodsFirst of all, three MOFs, i.e., Co/DOBDC, Ni/DOBDC, and Co3(HCOO)6, were synthesized and activated according to the preparation methods in the published literature, and the adsorption isotherms of Xe and Kr in three MOFs samples were measured by using physical adsorption instrument with a specially designed water circulating system to maintain a constant temperature (273 K). Then, these samples were irradiated with γ-ray (1.322 MeV) at a gamma dose rate of 0~1 kGy·h-1 at ambient temperature. Samples' properties, such as Henry constant, Henry selectivity and ideal adsorbed solution theory (IAST) selectivity of Xe/Kr, before and after irradiation, were characterized by X-ray diffraction (XRD) patterns and N2 adsorption measurements. Finally, the γ-ray radiation stability of Co/DOBDC, Ni/DOBDC and Co3(HCOO)6 were studied, and the pore properties (specific surface area and pore volume) before and after irradiation were compared.Results & ConclusionsExperimental results from the observed single-component Xe and Kr isotherms, Henry's constants, Henry's constant ratio and IAST selectivity of the sample, show that Co/DOBDC and Ni/DOBDC as adsorbents have the potential to adsorb and storage high concentration Xe whilst Co3(HCOO)6 has the potential for adsorption separation of Xe and Kr in low concentration. Radiation resistance test results show that the pore properties of Co/DOBDC and Ni/DOBDC change significantly after different doses of γ-ray irradiation, and the change degree of pore properties of Co/DOBDC is large than that of Ni/DOBDC whilst the pore properties of Co3(HCOO)6 basically do not change after γ-ray radiation at a total dose of 9 kGy, indicating that Co3(HCOO)6 can be considered as a potential adsorbent for Xe/Kr separation under radioactive conditions.  
        关键词：Metal-organic frameworks;Xenon and krypton;Adsorption separation;γ-ray irradiation   
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        发布时间：2024-10-25

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • “LaBr3（Ce）晶体探测器在核测井、环境监测、核医学等领域有广泛应用，专家利用Geant4工具包建立探测模型，研究影响探测效率的因素，为探测器设计提供参考。”
        CHEN Zhiqiang,CHEN Jingjing,SHU Shuangbao,YU Ziqiao,ZHANG Yuzhong,LANG Xianli
        Vol. 45, Issue 1, Article number: 010401(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010401
        摘要：BackgroundLaBr3(Ce) crystal is a new type of inorganic scintillator with excellent properties and is an excellent material for making scintillator detectors. LaBr3(Ce) detector has been widely used in nuclear logging, environmental monitoring, nuclear medicine, and other fields. Detection efficiency of the detector is an important index for the design and development of the detector.PurposeThis study aims to explore the factors affecting the detection efficiency of a LaBr3(Ce) detector by simulation.MethodsFirst of all, the detection model of the LaBr3(Ce) detector was established by using Geant4 toolkits. Then, factors affecting the detection efficiency of the detector, such as the shape and size of crystal cross section, position and the energy of the radioactive source, were studied in details.ResultsThe results show that the detection efficiency is related to the shape and size of crystal cross-section. The detection efficiency of rectangular section is lower than that of circular and square section; the larger the crystal radial size and the shorter the crystal length, the higher the detection efficiency. The detection efficiency of the LaBr3(Ce) detector is related to the energy of the ray: the higher the energy, the lower the detection efficiency. At the same time, the smaller the distance between the source and the detector, the higher the scintillation detection efficiency.ConclusionThe analysis of the influencing factors of detector detection efficiency has a certain reference value and guiding significance for the research and design of LaBr3(Ce) detectors.  
        关键词：LaBr3(Ce);GEANT4;Detection efficiency;Ray detection   
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        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “在核反应堆领域，专家设计实验装置，研究了矩形窄缝通道内受热表面污垢沉积特性，为解决传热性能恶化问题提供解决方案。”
        CHENG Cheng,DUAN Zhongdi,XU Wei,LIU Xiaojing,TANG Wenyong
        Vol. 45, Issue 1, Article number: 010601(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010601
        摘要：BackgroundWhen the reactor residual heat is removed under loss of coolant accident (LOCA), the negative solubility salt impurities enter the coolant, and the surface of the plate-type components is scaled, which seriously affects the heat transfer performance of the channel and even leads to channel blockage.PurposeThis study aims to understand the fouling characteristics on the heating surface of the narrow rectangular channel.MethodsAn experimental set-up was designed and built to collect fouling samples at the specific locations of the heating surface. Using calcium carbonate as a soluble impurity, the fouling process of the heating surface of a narrow rectangular channel with a cross-section of 60 mm×2 mm was experimentally examined. The microscopic morphology characteristics of the fouling at different locations of the channel and at different times were observed. The distribution characteristics of fouling thickness were measured, and the effect of fouling on wall heat transfer was investigated.Results & ConclusionsThe fouling morphology changes with time, and the fouling thickness at different locations is significantly different. The heat transfer coefficient of the channel first decreases and then tends to be stable with a decrease of 26.49%.  
        关键词：Loss of coolant accident;Narrow rectangular channel;Fouling deposition;Microtopography;Heat transfer   
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      • “在核反应堆建模领域，专家基于BEAVRS2.0.1基准题，构建了高保真压水堆堆芯模型，应用NECP-X和OpenMC程序进行建模计算，验证了程序的可行性和准确性。”
        SHEN Zhirui,SUN Qizheng,HE Donghao,PAN Qingquan,ZHANG Tengfei,PENG Lianghui,YANG Weiyan
        Vol. 45, Issue 1, Article number: 010602(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010602
        摘要：BackgroundWith the improvement of the understanding of the physical mechanism of neutron transport and the development of high performance computing technology, high-fidelity neutronics calculation has attracted widespread attention worldwide. Both deterministic method and Monte Carlo method are employed by various institutions to achieve high-fidelity goals. NECP-X code uses one-step deterministic method whilst OpenMC uses the Monte Carlo method.PurposeThis study aims to verify the feasibility and accuracy of both NECP-X and OpenMC in modelling high-fidelity reactor cores.MethodsBased on BEAVRS2.0.1 benchmark, two high-fidelity models for pressurized water reactor (PWR), i.e., MODEL 1 consisted of 21 fuel assemblies and MODEL 2 consisted of 193 fuel assemblies, were established. Then, NECP-X (one-step deterministic method) and OpenMC (Monte Carlo method) were respectively adopted in these two high-fidelity models to calculate the effective multiplication factor, the reactor power distribution and the control rod worth of different control rod assemblies inserted in the hot zero power (HZP) condition. Finally, calculated results were compared and analyzed.ResultsUnder the HZP condition, the effective multiplication factor deviation between NECP-X and OpenMC is less than 1.40×10-3. The effective multiplication factor deviation of different control rod assemblies inserted is less than 5.9×10-4, and the deviation of control rod worth is less than 4.9×10-4. The average relative deviations of the reactor power distribution between NECP-X and OpenMC are less than 0.6%.ConclusionsNumerical results calculated by two different codes are in good agreement with each other. The feasibility and accuracy of NECP-X and OpenMC in high-fidelity reactor core modeling are preliminarily verified in this study, which lays a foundation for future applications and improvements.  
        关键词：BEAVRS benchmark;NECP-X;OpenMC;Comparison and verification   
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      • “在快中子反应堆领域，专家建立了二氧化铀燃料与包壳材料的化学相互作用模型，为高燃耗燃料元件设计提供重要参考。”
        CHEN Qidong,GAO Fuhai
        Vol. 45, Issue 1, Article number: 010603(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010603
        摘要：BackgroundUranium dioxide fuel elements of fast neutron reactor operate under the conditions of high burnup, high neutron fluence rate, high line power and high temperature. Complex physical chemical interactions occur between fuel and the cladding materials. The establishment of fuel element chemical interaction model is very important for the design of high burnup fast reactor fuel element.PurposeThis study aims to establish a chemical interaction model between fast reactor fuel and cladding materials under high burnup.MethodsEmphasis was placed on the chemical interaction phenomenon of the oxide fuel elements of fast neutron reactors. Firstly, the chemical interaction models of uranium dioxide interacted with austenitic stainless steel and ferritic-martensitic steel cladding materials were established by using a dynamic model. Then, special fuel element performance analysis program FIBER-Oxide, developed by China Institute of Atomic Energy (CIAE), was employ to verify these chemical interaction models by experimental data.ResultsThe corrosion model of fast reactor uranium dioxide fuel and austenitic stainless steel can successfully predict the cladding corrosion with maximum burnup of 10.8at% and irradiation damage of 87.5 dpa. The corrosion model of fast reactor uranium dioxide fuel and ferritic-martensitic steel can successfully predict the cladding corrosion with maximum burnup of 9.3at% and irradiation damage of 76.6 dpa.ConclusionsThe results of this study provide important reference value for the design and performance prediction of high burnup uranium dioxide irradiation elements and fuel elements of demonstration fast reactor.  
        关键词：Fast reactor fuel element;Pellet cladding interaction;Corrosion cracking;High burnup   
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      • “在核应急救援演练领域，专家建立了基于AHP权重分析的模糊评估模型，为评估救援演练效果提供解决方案。”
        RUAN Fang,SHEN Chao,CHENG Yuan,ZHU Jingxian,LUAN Fei,WANG Jianye
        Vol. 45, Issue 1, Article number: 010604(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010604
        摘要：BackgroundNuclear emergency rescue drill evaluation is the main basis for testing and improving the emergency rescue ability of nuclear emergency team. To date, nuclear emergency evaluation has mainly focused on individual aspects such as emergency response capabilities, radiation monitoring, medical rescue and decontamination, etc. Little attention was paid to the complete evaluation index system and model.PurposeThis study aims to evaluate the effect of nuclear emergency rescue exercise in real time by establishing a fuzzy evaluation model of nuclear emergency rescue exercise based on analytic hierarchy process (AHP).MethodsAccording to the nuclear emergency rescue process, based on the nuclear emergency rescue team structure, task classification, drill effects and personnel safety requirements, the Delphi method was used to establish the nuclear emergency rescue drill evaluation index system. The fuzzy comprehensive evaluation method (FCE) based on the AHP method was employed to carry out weight allocation and construct a multi-level fuzzy comprehensive evaluation model. Finally, the M310 nuclear power plant (NPP) was taken as an example to verify the established evaluation model.ResultsThe evaluation results on M310 NPP effectively examine the response ability and the actual drill effect of the emergency rescue team, and reveal the problems and deficiencies during the drill.ConclusionsThe effectiveness of established evaluation model is verified in this study.  
        关键词：Nuclear emergency rescue drill;Evaluation index system;AHP weight analysis;Fuzzy comprehensive evaluation method   
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      • “在核安全领域，专家基于COMSOL软件建立了流-热-固耦合模型，仿真研究了IVR技术下反应堆压力容器双层熔融池演变过程，为核电厂严重事故下压力容器完整性提供解决方案。”
        ZHU Guangyu,MIN Jinkun,JING Jianping,WANG Kunpeng,LIU Fudong
        Vol. 45, Issue 1, Article number: 010605(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.010605
        摘要：BackgroundIn-vessel Retention (IVR) refers to the prevention of pressure vessel melt-through failure by injecting cooling water into the gap between the pressure vessel and the heat insulation layer during a serious accident in a nuclear power plant. When the double-layer corium pool formed in the lower head of the reactor pressure vessel (RPV), the lower head in contact with the metal layer may fail due to the heat accumulation in the metal layer.PurposeThis study aims to build a computational model by numerical simulation to investigate the thermal hydraulic characteristics of the double-layer corium pool in pressurized water reactor (PWR).MethodsBased on the design parameters of current large third generation PWR, the calculation model of the fluid-heat-solid coupling double-layer corium pool was established by using COMSOL Multiphysics code. The upper surface of metal layer was considered as the radiation boundary condition, and the outside of the lower head was set as forced convection cooling.ResultsSimulation results show that a natural convection main flow forms in the oxide layer in stable two-layer corium pool, and a mass of vortexes exist in the metal layer. The lower head in contact with the oxide layer does not melt obviously whilst significant melting occurs in the lower head area in contact with the metal layer due to the rising temperature. The completeness of the pressure vessel is maintained under normal cooling conditions.ConclusionsThe IVR design is proved efficient to protect the pressure vessel form melt failure during a serious accident.  
        关键词：IVR;Severe accident;Corium pool   
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