最新刊期
      卷 46 ， 期 12 ， 2023

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • “上海光源BL02U2线站新增掠入射衍射仪，完善了实验条件，为材料表面科学研究提供丰富平台。”
        LIAO Keliang,ZHENG Xu,LI Zhao,XUE Zhipeng,YIN Guangzhi,ZHANG Xingmin,LI Xiaolong,GU Yueliang,ZHU Peiping
        Vol. 46, Issue 12, Article number: 120101(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120101
        摘要：BackgroundTwo X-ray diffractometers manufactured by HUBER company are installed at BL02U2 beamline of Shanghai Synchrotron Radiation Facility (SSRF).PurposeThis study aims to develop a new grazing incidence diffractometer installed between the two HUBER diffractometers to further satisfy the needs of users for grazing incidence diffraction experimental methods.MethodsThe overall scheme of the grazing incidence diffractometer was introduced, followed by detail discussion on several important modules such as high-precision, high-load and large-stroke linear stage, three-dimensional adjustment platform for a detector, sample stage system, and the control system. A compatible operation of the three diffractometers was realized, and the MoS2 sample was taken as an example to obtain a typical experimental result of the grazing incidence diffractometer.ResultsThe grazing incidence X-ray diffractometer has been in operation for more than two years. The X-ray energy range of the diffractometer is 4.8~28 keV. The temporal resolution of the detector is 50 ms, and the maximum detection angle is 52°. Experimental results of MoS2 sample shown that the nanosheets are more likely to accumulate on the surface of silicon wafers along the (001) crystal plane.ConclusionsThe grazing incidence X-ray diffractometer developed in this study improves the experimental conditions for grazing incidence diffraction and expands the experimental platform for material surface science research at SSRF.  
        关键词：X-ray diffraction;Synchrotron radiation;Precision instrument   
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        发布时间：2024-10-25

        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • “在月球探测领域，研究人员提出了一种新方法，成功提取了嫦娥二号γ射线谱仪数据中的微弱氢特征γ射线信息，并预测了月球表面可能存在大量结构水的区域。”
        LI Yonghui,ZHAO Jiankun,JIANG Shuang,WANG Feiliang,WU Hexi,LIU Yibao
        Vol. 46, Issue 12, Article number: 120201(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120201
        摘要：BackgroundWater is the primary resource required for the exploitation of lunar resources. Investigating the distribution of water on the surface of the moon has become a focal point in the lunar exploration plans of several nations.PurposeThis study aims to quantify the presence of hydrogen and analyze its spatial distribution on the lunar surface using data from the Chang'E-2 gamma-ray spectrometer (CE2-GRS).MethodsFirstly, an analytical method combining branch specific stripping with the nonlinear least-square fitting Gaussian function was proposed to subtract the characteristic γ rays of interfering nuclides (214Bi@2.204 MeV, 27Al@2.210 MeV, 49Ca@2.371 MeV) ranging from 2.1 MeV to 2.5 MeV. Then, a characteristic function between the abundance and counts of aluminum γ rays around the moon was established to subtract the counts of aluminum in the mixed peak. Finally, the spatial distribution of hydrogen γ rays for counts per 3 s on the whole lunar surface was obtained.ResultsThe analysis results show that high-value characteristics exhibited in some areas, including the Aiken basin, Mare Ingenii, Mare Imbrium, and Oceanus Procellarum, are approximately 2.6 times the average value of hydrogen counts among the 14 major maria. Comparison between the distribution characteristics of hydrogen elements on the lunar surface and the data of epithermal neutrons from Lunar Prospector (LP) reveals a highly negative correlation between the distribution characteristics of the two in these regions.ConclusionsThe distribution characteristics of hydrogen elements on the lunar surface further predict that there may be a large amount of structural water in the Mare Ingenii, Mare Imbrium, and Oceanus Procellarum, formed by the combination of hydroxyl groups or molecular hydrogen (H2), achieving a better understanding of the orbit γ deep mining and scientific application of energy spectrum data.  
        关键词：CE2-GRS;Decay branching ratio;Nonlinear least-square fitting;Distribution of hydrogen   
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        发布时间：2024-10-25
      • “俄罗斯NICA项目中桶状抽样型电磁量能器研究取得进展，模拟分析了入射位置、闪烁体层数对探测器性能的影响，为探测器设计提供参考。”
        ZHU Jin,PENG Xiaoyu,LUO Siyuan,XIAO Wancheng,HE Lie,LIU Yuchen,LUO Fengjiao,XIAO Min,WANG Xiaodong
        Vol. 46, Issue 12, Article number: 120202(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120202
        摘要：BackgroundThe barrel-sampled electromagnetic calorimeter (Ecal) is an important part of the Multi-Purpose Detector (MPD) in Nuclotron-based Ion Collider fAcility (NICA) that is being built in Russia. It is primarily used to detect energy, time, and position information of electrons and photons in the energy domain from 10 MeV to a few GeV. MPD-Ecal is comprised of 2 400 modules with 16 towers per module. Each tower is made up of alternating layers of 211 scintillator sheets and 210 lead sheets, as well as 16 wave-length shift fibers.PurposeThis study aims to evaluate the performance, such as energy resolution, time resolution, and coordinate resolution, etc., of the Ecal by simulation.MethodsThe Geant4 software was employed to simulate single-energy electron incident on Ecal to examine the effects of several parameters on the performance of Ecal. Influences of the position of the particle incidence point, the number and thickness of the scintillator and lead layers, the polish of the optical fibre end-face, and the energy and type of incident particles on the energy deposition and resolution, time distribution and time resolution, and coordinate resolution were investigated in details. Finally, the time resolution of a single tower was simulated using the natural cosmic ray package, and the tower's expected time resolution in the cosmic ray test was obtained.ResultsAs the electron incidence position moves from the edge to the center of the module, the energy deposition within the scintillator rises from 718 MeV to 758 MeV. With a limited tower length of 415.5 mm, increasing the number of scintillator layers decreases the energy resolution of the module, improves the time resolution of the tower, and worsens the coordinate resolution of the Ecal. Taking into account the performance of the Ecal gauge, the optimal number of scintillator layers in the tower is 211. SiPM detects 42% more photoelectrons at a polish of 0.6 when the fiber end is coated with a reflective material than when it is not. As the polish of the fiber end-face increases, so does the number of photoelectrons detected by the SiPM, and the time resolution of the tower improves. When the fibre end-face polish is 1.0, the time resolution of the tower is less than 103 ps while time resolution of the tower (with 211 layers) in the cosmic ray is 185 ps.ConclusionsThe time and coordinate resolutions of Ecal improve with increasing electron energy under the same circumstances.  
        关键词：Energy resolution;Time resolution;Coordinate resolution;GEANT4   
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        发布时间：2024-10-25
      • “在中子照相领域，专家提出了一种改进的图像几何不锐度修正方法，有效提升了图像质量，为高分辨率中子照相提供技术支撑。”
        WU Huajie,GAN Quan,LYU Yongqiang,WANG Qihong,WU Yifan,SONG Jing,FDS Team
        Vol. 46, Issue 12, Article number: 120203(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120203
        摘要：BackgroundDue to the specific imaging structure of neutron imaging system, the geometric unsharpness is unavoidable in neutron photographic images after imaging.PurposeThis study aims to design a geometric unsharpness correction method for neutron photographic image based on improved Richardson–Lucy (RL) algorithm.MethodsFirst, according to the geometric unsharpness of the neutron photographic image, the mathematical model of the point spread function (PSF) was established. Then, the Laplace operator and median filter were used to remove the PSF related gamma spots noise (GSN) in the image, and the neutron photographic image was restored by RL algorithm. Finally, the restoration quality of neutron photographic images of the line-pair sample was evaluated using average gradient (AG) and spatial frequency (SF).ResultsThe results of the line-pair sample demonstrate that compared with four existing correction algorithms of geometric unsharpness, the proposed method improves AG and SF by 60.23% and 29.90%, respectively.ConclusionsThe proposed method of this study can effectively correct the geometric unsharpness caused by the amplification of gamma spots noise in the process of neutron photographic image restoration, providing an important technical support for performing high-resolution neutron radiography.  
        关键词：Neutron photographic image;Image restoration;Geometric unsharpness;Richardson–Lucy algorithm;High resolution   
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        发布时间：2024-10-25

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • “最新研究揭示了镍、铁、钨合金在反应堆中抗辐照性能的差异，为核反应堆材料选择提供重要参考。”
        YING Hong,WEN Ali,ZHOU Suiru,HAI Xue,ZHANG Wenfeng,REN Cuilan,SHI Haining,HUANG Hefei
        Vol. 46, Issue 12, Article number: 120301(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120301
        摘要：BackgroundNickel-, iron- and tungsten-based alloys are commonly used as structural materials of reactors. During their operational life, these alloys undergo intense neutron irradiation.PurposeThis study aims to analyze the post-irradiation defect evolution and its mechanisms in these materials for comprehending the effects of irradiation on them.MethodsThe displacement cascades in nickel, iron, and tungsten were examined at various temperatures (300⁓500 K), primary knock-on atom (PKA) energies (<20 keV), and directions (<135>, <122> and <100>) by using molecular dynamics (MD) simulations. Firstly, the model was initially relaxed at each specified temperature under a canonical ensemble for 10 ps, applying periodic boundary conditions in every direction. Then, an atom was randomly chosen as a PKA and assigned kinetic energy to initiate the cascade collision simulation in the micro-canonical ensemble. Finally, the Open Visualization Tool package was employed for visualization and data analysis of the irradiation cascade processes.ResultsThe simulation results reveal that nickel and iron exhibit similar steady-state defects. At lower PKA energies (<5 keV), nickel exhibits marginally fewer defects than iron. However, as the PKA energy surpasses 5 keV, the number of defects in nickel becomes slightly more than that in iron. Furthermore, under identical irradiation conditions, tungsten demonstrates superior radiation resistance, with fewer steady-state defects when compared with both nickel and iron.ConclusionsThe defect evolution during various cascade displacement phases in three metals and their defect recombination rates are crucial to understanding the disparities in radiation damage resilience. The derived results help to comprehend the radiation characteristics of these metals. Additionally, the primary radiation damage dataset compiled for these metals lays a foundation for further larger-scale simulations of their radiation attributes using rate theory or cluster dynamics methods.  
        关键词：nickel;Iron;Tungsten;Neutron irradiation;Primary radiation damage;Molecular dynamics   
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        发布时间：2024-10-25

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • “在地质勘查和放射性污染调查领域，研究人员设计了一种新型双能定向γ辐射取样探头，有效提高了放射性元素含量测量的准确性。”
        LIU Hongwu,GE Liangquan,WU Jitong,YANG Xiaofeng,DENG Zhipeng,TANG Chuanfeng,XIONG Maolin
        Vol. 46, Issue 12, Article number: 120401(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120401
        摘要：BackgroundThe targeted acquisition of the radioactive element content or radioactivity in a radioactivity is an important task in geological exploration and radioactive pollution investigation. During the process of targeted gamma radiation sampling, gamma rays from non-target areas significantly interfere with the measurement results.PurposeThis study aims to design a dual-energy targeted gamma radiation sampling probe that uses a cerium bromide scintillation detector on the basis of the difference in the linear attenuation coefficients of the high- and low-energy gamma rays from the same radioactive decay series in the lead shielding layer of the detector.MethodsFirstly, Monte Carlo (MC) numerical simulations were employed to determine the optimal lead shielding layer thickness for the dual-energy targeted gamma radiation sampling probe detecting targets of the 0.609 MeV and 1.764 MeV gamma rays emitted by 214Bi. Then, the directional proportionality coefficients were calculated and applied to obtaining 0.609 MeV gamma ray counts of dual energy γ radiation probe within lead shielded angle. Finally, MC numerical simulations with four types of interfering radiation sources and physical experiments with two radium sources were conducted to validate the results that calculated using the directional proportionality coefficients.ResultsThe simulation result of optimal lead shielding layer thickness for the dual-energy targeted gamma radiation sampling probe is 6 mm, and the calculated directional proportionality coefficients of a and A are 0.268 and 0.451, respectively. Validation results show that the relative error between the counts for the 0.609 MeV gamma rays within the shielded angle and the net peak area counts measured with the dual-energy targeted gamma radiation sampling probe for two radium sources is within ±2.52% with average relative error of 0.63%. The relative errors between the measured uranium content and recommended values in the tested models are all less than 5%.ConclusionsThe dual-energy targeted gamma radiation sampling results for a radioactive mixed standard model and three radioactive models indicated that the designed dual-energy targeted gamma radiation sampling probe is capable of targeted gamma radiation sampling.  
        关键词：Dual-energy targeted gamma radiation sampling technique;Uranium exploration;Directional proportionality coefficient   
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        发布时间：2024-10-25
      • “在EAST托卡马克装置上，研究人员设计了一套激光吹气微量杂质注入系统，实现了对等离子体杂质输运的精确控制，为提升等离子体约束性能与保障装置安全提供重要支撑。”
        FAN Yu,ZHAO Yuhong,ZHANG Hongming,LYU Bo,LIN Zichao,SHEN Yongcai,YIN Xianghui,WANG Fudi,FU Jia,JI Huajian,ZENG Chao,MAO Liyu,SUN Bo
        Vol. 46, Issue 12, Article number: 120402(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120402
        摘要：BackgroundStudying the transport behavior of impurities in plasma and developing effective impurity control methods are important for achieving high-performance plasma discharge and ensuring the safe operation of the device.PurposeThis study aims to design a control system for the experimental advanced superconducting Tokamak (EAST) laser blow-off (LBO) impurity system.MethodsA new automatic control process was adopted to enable to inject tracer particles of different elements into the EAST plasma repeatedly, quantitatively, and controllably. An accurate control of the focusing lens displacement and laser triggering time were achieved through the STM32 microcontroller system and its output PWM waves for stepper motor driving, hence the diameter of the laser spot was adjustable to change the amount of impurities injected. Finally, the designed control system for LBO was tested in staging environment to verify its practicability and accuracy.ResultsThe test results show that the system can rapidly detect the external trigger signal and achieve precise timing, with less than 0.4 mm position error for laser spot focusing.ConclusionsThe design of control system meets the requirements of the laser blowing impurity injection experiment. This study is of considerable significance for research on EAST plasma impurity transport.  
        关键词：Laser blow-off impurity injection system;Impurity transport;STM32;Control system   
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        发布时间：2024-10-25
      • “在辐射监测领域，大面积塑料闪烁体探测器的阈值电压确定方法，提高了探测效率一致性，降低了最小可探测活度。”
        CHEN Jiutao,SONG Yushou,XU Rui,SONG Runzhou,CHEN Shengqiang
        Vol. 46, Issue 12, Article number: 120403(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120403
        摘要：BackgroundLarge-area plastic scintillators are widely used in radiation monitoring. They are typically employed as gamma radiation counters through signal over-threshold detection. The value of the threshold voltage affects the detector efficiency and minimum detectable activity. When rays are incident at different positions of the large-area plastic, the photon collection efficiencies generated through collecting end pair differ, leading to differences in the detector efficiency.PurposeThis study aims to explore appropriate threshold voltage to reduce the differences and maintain a low minimum detectable activity (MDA), hence achieving high detection efficiency for large-area plastic scintillator.MethodsFirstly, an energy spectra acquisition system was designed using STM32F429 produced by STM semiconductor as the main control chip and a counter for detector efficiency testing of large-area plastic scintillator in size of 400 mm×300 mm×50 mm. Then, the reasonable threshold voltage was determined according to the background energy spectra of the large-area plastic scintillator, the energy spectrum of the 60Co and 137Cs sources at different positions of the large-area plastic scintillator with acquisition time of 3 min, and signal-amplification relationship.ResultsThe determined threshold voltage using above mentioned method for 60Co source is 93.7 mV. To achieve high detector efficiency and low MDA for the large-area plastic scintillator, the best determined threshold voltage for 60Co source is 95 mV. At this voltage, the detector efficiency for 60Co source is 22%, the MDA is 78 Bq.ConclusionsThe proposed method has reference value for large-area plastic scintillation designing and manufacturing detectors.  
        关键词：Plastic scintillator;Threshold voltage;Detector efficiency;Minimum detectable activity   
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        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • “在放射性废物测量领域，研究人员提出了基于神经网络的新型活度测量方法，大幅提高了测量精度并缩短了时间，为低、中水平放射性固体废物的测量提供了技术支撑。”
        SHU Minxiang,SHAN Chenyu,GU Weiguo,WANG Dezhong
        Vol. 46, Issue 12, Article number: 120501(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120501
        摘要：BackgroundDuring the operation of nuclear power plants, a large amount of low and intermediate level waste (LILW) is generated, which is usually prepared into 200-L and 400-L waste drums. To ensure the safe disposal of these waste drums, they must be analyzed to determine the type and activity of the nuclides contained within them. Non-destructive assay (NDA) has been widely used in the detection of waste drums in nuclear power plants, along with segmented gamma scanning (SGS) and tomographic gamma scanning (TGS). However, the low measurement accuracy of SGS and the long measurement time of TGS limit the practical application of these methods.PurposeThis sudy aims to shorten the measurement time while maintaining high measurement accuracy by proposing a new neural network-based method for measuring the activity of waste drum.MethodsWhen the waste drum was filled with a uniform distribution of medium and rotated at a constant speed during measurement, the point source was equivalent to a ring source. The equivalent ring source in the waste drum possessed an activity equal to the total activity of all sources. The neural network model is established, the count rate of the detector at different positions is used as input, and the radius of the equivalent ring source is used as output. Finally, the total activity of the waste drum is calculated. The simulated measurement is carried out in a 400-L waste drum, the medium is concrete, the radioactive source is Co-60, and 50 groups of single-source and 10 groups of multi-source are generated randomly. Different methods are used to reconstruct the activity of the waste drum.ResultsWhen there is only one radioactive source in the waste drum, the mean relative error (MRE) of activity reconstruction by the new method is 4.26%, which is much lower than that of SGS (68.15%) and close to that of TGS with 60 grids (3.97%). When there are multiple radioactive sources in the waste drum, the MRE of activity reconstruction by the new method is 24.27%, which is lower than that of SGS (48.02%) and close to that of TGS with 60 grids (28.61%). This new method achieves the equal measurement accuracy of TGS but reduce the measurement time to 1/20 of TGS.ConclusionCompared to traditional measurement methods, the new method greatly shortens the measurement time while maintaining high precision, thereby providing technical support for the measurement of LILW.  
        关键词：LILW;NDA;Activity reconstruction;Neural network;Equivalent ring source   
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      • “在电解水制氢领域，研究人员开发了新型Ba-Si-Ca体系密封玻璃，有效提高了固体氧化物电解堆的热稳定性和冷热循环性能，为商业化推进提供技术支撑。”
        LIAO Zihao,CHENG Fupeng,LEI Jinyong,PAN Jun,HUANG Xurui,YANG Yiping,YU Fengyuan,MA Chengguo,GUAN Chengzhi,XIAO Guoping,WANG Jianqiang,XIONG Bo,CHEN Yifan
        Vol. 46, Issue 12, Article number: 120502(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120502
        摘要：BackgroundSolid oxide electrolysis cell (SOEC) offers a promising method for converting H2O into H2 at high temperatures ranging from 600 °C to 850 °C. Glass sealants, which are crucial materials in SOEC, fulfill most criteria for an ideal sealant when appropriate glass components at suitable stoichiometric proportions are selected. Nevertheless, they exhibit certain drawbacks, including limited stability, elevated gas leakage rates, and suboptimal thermal cycling performance during the SOEC operation.PurposeThis study aims to evaluate the performance of Al2O3 added Ba-Si-Ca sealant for SOEC.MethodsFirstly, a new Ba-Si-Ca system sealing glass (glass-P) was developed to enhance its properties, such as the coefficient of thermal expansion, glass transition, and softening temperatures, and a series of alumina additions to glass-P, intended for use as the SOEC sealant, were prepared using curtain coating. Then, the coefficients of thermal expansion of these sealants were evaluated using a thermal expansion instrument. The leak rate of the sealants, as well as the impact of different alumina additives on the material's thermal shock resistance and chemical stability, were assessed via a 1-cell stack measurement for extended SOEC operation. Finally, the elemental distribution of the specimen was observed using scanning electron microscopy coupled with energy-dispersive X-ray spectroscopy (EDS).ResultsThe experimental results show that the leakage rate of the glass P-10 sealant is measured at 5.54×10-3 sccm∙cm-1, which is lower than that of glass P. After undergoing ten thermal cycles, the leakage rate of glass P-10 is found to be 2.275×10-2 sccm∙cm-1, lower than that of the others. An open circuit voltage (OCV) of approximately 1.169 V is recorded for glass P-10 after a 1 053-h test.ConclusionsThe addition of alumina to glass P significantly enhances the sealant's thermal stability and gas tightness.  
        关键词：Sealant;Solid oxide electrolysis cells;Gas leakage;chemical stability   
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      • “在同位素电源领域，研究人员设计了一种电加热模拟热源，可有效模拟通用热源性能，为同位素温差电池性能评价提供参考。”
        WANG Hongyu,XU Zhiheng,WANG Jiyu,LIU Shichao,LU Hongbo,LI Xinyi,LIU Yunpeng,TANG Xiaobin
        Vol. 46, Issue 12, Article number: 120503(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120503
        摘要：BackgroundA general-purpose heat source (GPHS) is the most established heat source module for radioisotope thermoelectric generators (RTGs) and a key reference for the equivalence of electrically heated analog heat sources during the development and testing of radioisotope power supplies.PurposeThe study aims to develop a highly efficient electric heating simulation heat source to meet the requirements for equivalent testing and verification of non-nuclear units of radioisotope power systems.MethodsFirstly, an electrically heated analog heat source was designed and imitated based on various actual GPHS performance parameters. Based on the simulation calculations, the thermodynamic equivalent substitutability between the simulated heat source and real GPHS in terms of material and dimensional differences was evaluated. Then, the performance of its operation in different application scenarios was analyzed, and an optimized application environment was proposed. Finally, based on the experimental test results, the uniformity of the thermal output characteristics of the imitation GPHS-simulated heat source was compared with that of a real GPHS, and the practical application characteristics of the imitation GPHS in RTGs were also evaluated.ResultsAt an input power of 250 W, the average surface temperature of the GPHS-simulated heat source reaches 515 K. The temperature variation trend with power is consistent with that of the simulation results. Experimental test results show that the energy conversion efficiency of the RTG module is increased to ~6% with a 250-W heat source power supply.ConclusionsThe proposed and constructed good equivalent simulated GPHS heat source with reference to the thermal properties of a real GPHS can be applied to RTGs and provides an effective and unified reference standard for the performance evaluation of radioisotope power sources.  
        关键词：Radioisotope;Simulated heat source;COMSOL simulation;General-purpose heat source;Radioisotope thermoelectric generator   
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        发布时间：2024-10-25
      • “在高能粒子辐照损伤领域，专家总结了电子能损效应对靶材料损伤的影响规律，为后续研究提供新方向。”
        XU Jiangwei,ZHANG Chao,MAO Fei,ZHANG Fengshou
        Vol. 46, Issue 12, Article number: 120504(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120504
        摘要：Energy loss during interactions between high-energy particles and target materials mainly consists of nuclear and electronic energy losses. Electronic stopping and electron-phonon coupling effects are two different mechanisms that reflect electronic energy loss effects. To accurately simulate the irradiation damage process of high-energy particles, it is necessary to solve the key scientific problem of the influence of electronic energy loss on irradiation damage. This paper reviews the most recent progress on the irradiation damage behavior study of several key structural materials under the influence of electronic energy loss effects, elaborates the effects of electronic stopping, electron-phonon coupling, and electronic thermal conductivity on irradiation defects. The influence laws of electronic energy loss effects on the irradiation damage of target materialsare summarized and the existing problems in the research of high-energy particle irradiation of target materials are highlighted. Finally, the prospectives are outlined for future research directions.  
        关键词：Electronic energy loss effect;Irradiation defect;Two-temperature model;Electron-phonon coupling;Collision cascades   
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        发布时间：2024-10-25

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “在核聚变装置中，基于闪烁体的快离子损失探针（FILD）通过FILDSIM程序，将诊断图像转化为速度空间分布，为评估和控制离子回旋共振加热下的快离子损失提供解决方案。”
        WANG Shusong,HUANG Juan,CHANG Jiafeng,ZHANG Xinjun,GAO Wei,FU Jing,SUN Yanxu,SHI Chang,WANG Xihui,ZHANG Zixin
        Vol. 46, Issue 12, Article number: 120601(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120601
        摘要：BackgroundScintillator-based fast-ion loss detector (FILD) can measure the velocity-space distribution of fast-ion loss and are key in studying the control mechanism of fast-ion loss in nuclear fusion devices.PurposeThis study aims to obtain the velocity-space distribution of fast-ion loss from corresponding FILD data and evaluate the capacity of current FILD probe for the further improvement of diagnostic design.MethodsThe FILDSIM code was employed to establish the linkage between the fast-ion image digitized by FILD and the velocity-space distribution of fast-ion loss. The detection coverage of fast ions on the scintillator was assessed through reverse tracing of the lost fast ions, considering the geometry of the FILD probe as well as the pitch angle and gyroradius of fast ions entering the pinhole of the FILD probe.ResultsThe obtained velocity-space distribution of fast-ion loss under ICRH indicates that the energy of lost fast hydrogen minority ions is above 200 keV. Moreover, analysis shows that the geometry of the probe, particularly the shell behind the scintillator, obstructs the diagnostic detection range, creating a null region on the scintillator.ConclusionsThe acquisition of the velocity-space distribution of fast-ion loss lays the foundation for further evaluation and control of fast-ion loss under ion cyclotron resonance heating. In addition, the investigation of the probe detection range provides a basis for upgrading diagnostic systems.  
        关键词：Fast-ion loss detector (FILD);FILDSIM;Ion cyclotron resonance heating (ICRH);Velocity-space distribution   
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      • “在不确定性分析领域，专家利用BP神经网络和MCMC抽样，建立了适用于子通道程序的不确定性量化分析方法。”
        HE Xin,SONG Meiqi,LIU Xiaojing
        Vol. 46, Issue 12, Article number: 120602(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120602
        摘要：BackgroundTraditional safety analysis methods rely on expert advice and user self-evaluation, lacking the ability to quantify output uncertainty. In contrast, the best estimation plus uncertainty (BEPU) methodology can quantify the uncertainty of the output, thereby avoiding unnecessary conservative assumptions and improving the economic viability of nuclear power. It is now widely used in the design and safety analysis of nuclear reactors. However, owing to the cognitive limitations of science and numerical approximation in programs, most thermal-hydraulic programs lack sufficient input uncertainty information related to internal models, often relying on expert advice.PurposeThis study aims to investigate the uncertainty quantification methodology for model parameters in sub-channel codes using Markov Chain Monte Carlo (MCMC) sampling.MethodsFirstly, the PSBT void fraction distribution experiments were employed to evaluate the prediction ability of the subchannel program COBRA-IV, and a Python-based uncertainty analysis methodology was developed to quantitatively analyze the model parameter uncertainties that affect the void fraction. Then, the model parameters were assumed to be independent, with their uncertainties following a normal distribution. Based on the Bayesian principle, the most likely maximum a posteriori probability function (PDF) of the model parameters were obtained by combining the prior and observed information, despite the limited actual uncertainty information. Finally, an MCMC sampling methodology was adopted to solve the Bayesian relation, and the statistical uncertainty information of the model parameters were obtained using a stable a posteriori Markov chain, which requires at least 104 magnitudes to achieve convergence and the corresponding forward program runs. Therefore, to reduce the calculation cost and improve the calculation efficiency, a high-precision adaptive BPNN surrogate model was constructed to replace the complex and time-consuming forward program code. Furthermore, a set of uncertainty quantification methods with Python was developed to simultaneously quantify the uncertainty of the model parameters using a statistical method. During the selection of a slip model we discovered that both the slip ratio and turbulence mixing coefficient significantly affected the void fraction. Therefore, we developed.ResultsThe results indicate that after obtaining the uncertainty of the model parameters, the 95% confidence interval of the results generated by the forward propagation of input uncertainty enveloped the experimental values well. Furthermore, by incorporating the mean value of the model parameter uncertainties, obtained via uncertainty quantification, the modified model output exhibited a closer agreement with the experimental values than with the reference values.ConclusionsThe uncertainty quantification analysis methodology established in this study can be applied to the uncertainty analysis of subchannel program model parameters.  
        关键词：Markov chain Monte Carlo sampling;Surrogate model;Uncertainty quantification;Void fraction;Inverse problem solving   
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      • “钠冷快堆二回路保护系统研究取得进展，建立了大泄漏钠水反应模型，验证了模型准确性，为保护系统设计提供参考。”
        BAI Xi,SUN Peiwei,LUO Gang,CAO Huasong,WEI Xinyu
        Vol. 46, Issue 12, Article number: 120603(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120603
        摘要：BackgroundThe sodium-cooled fast reactor adopts the three loops design with sodium-sodium-water. When a double-ended guillotine (DEG) break occurs in the steam generator (SG) tube, a large leakage sodium-water reaction (SWR) accident occurs, which threatens the safety and integrity of the secondary loop. A protection system is therefore designed to ensure secondary loop integrity.PurposeThis study aims to analyze the influence of protection system critical parameters on the large leakage SWR with paralleling SGs.MethodsFirst of all, a large leakage SWR model, including the water/steam leakage rate, hydrogen bubble growth, pressure wave propagation, and protection system models were established. Then, the large leakage SWR model was verified using the experimental data, and the 3-DEG large leakage SWR was simulated on the basis of the secondary loop structure. The integrity of the secondary loop and the protection system response were analyzed. Finally, a sensitivity analysis was performed for the critical parameters of the protection system, including the bursting pressure of liquid rupture disks, bursting delay time of rupture disks, location of liquid rupture disks, length of the release pipe, and volume of the primary accident discharged tank. Parameters with key influence on the integrity of the secondary loop and the protection system response were determined.ResultsThe 3-DEG large leakage sodium water reaction accident results in a peak pressure of 2.003 MPa in the reaction zone and 1.329 MPa in the critical equipment of the secondary circuit except for the reaction zone. The smaller bursting pressure and delay time, and the location of liquid bursting disks at the bottom chamber and the release pipe shorter length are more conducive to the integrity of the secondary loop and the protection system response.ConclusionsThis study provides a reference value for the design requirements of large leakage SWR protection systems with paralleling SGs.  
        关键词：Sodium-cooled fast reactor;Large leakage sodium-water reaction;Paralleling steam generator;Protection system;Sensitivity analysis   
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      • “西安交通大学核工程计算物理实验室开发的NECP-SARAX系统，在快堆堆芯物理特性分析上表现优异。针对TULIP程序在快谱问题计算分析上的精确性，选取了147组临界实验装置进行计算分析，发现对于带有厚反射层的实验装置，TULIP程序计算keff和蒙特卡罗程序计算值的偏差超过10-2。通过优化TULIP程序的共振计算策略和非共振区计算方法，改进后的程序对于快谱系统具有良好的计算分析能力。”
        CHEN Wenjie,DU Xianan,WANG Rong,ZHENG Youqi,WANG Yongping,WU Hongchun
        Vol. 46, Issue 12, Article number: 120604(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.120604
        摘要：BackgroundNECP-SARAX is a neutronics analysis code system for advanced reactors developed by the Nuclear Engineering Computational Physics Laboratory team of Xi'an Jiaotong University. In the past few years, a considerable amount of verification and validation work has been done based on CEFR, PHENIX, SUPERPHENIX, JOYO MK-I, ZPR, and ZPPR reactors. The results indicate that NECP-SARAX offers high performance for fast spectrum reactor analysis. Meanwhile, the fuel and control rod assemblies of these reactors are used for verification of the cross-section generation code TULIP. While TULIP has demonstrated promising preliminary results in fast spectrum system analysis, a comprehensive systematic verification and validation process remains essential.PurposeThis study aims to validate the applicability of TULIP code for various fast spectrum systems.MethodFirstly, a total of 147 critical experiment benchmarks were selected from ICSBEP and used for analysis. The initial results demonstrated that the keff bias between TULIP and Monte Carlo codes exceeded 10-2 for an experimental benchmark with a thick reflector. Then, a homogeneous two-nuclide problem simplified from the HMF021-002 benchmark was subsequently used to analyze this phenomenon, and the intermediate-weight nuclides had resonance-like fluctuating scattering cross sections above the resonance energy. Finally, to address this phenomenon, the TULIP code was undergone enhancements, mainly focusing on optimizing the resonance calculation strategy and method using ultra fine group to deal with thee self-shielding effect of resonance-like cross sections in the non resonant region under high loading of intermediate-weight nuclides.ResultsIn a fast spectrum system with a large amount of structural material, the self-shielding effect of the resonance-like cross section of the intermediate-weight nuclides above the resonance range becomes non-negligible. The optimized TULIP method reduces the keff bias to within 3×10-3 for these benchmarks with a thick reflector.ConclusionsNew numerical results indicate that the enhanced TULIP code has good performance for various fast spectrum system analyses.  
        关键词：TULIP code;ICSBEP benchmark;Intermediate-weight nuclide;Nonresonance energy;Resonance-like cross section   
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