最新刊期
      卷 46 ， 期 3 ， 2023

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • “X射线串行晶体学发展迅速，但数据筛选效率低。研究者基于卷积神经网络，构建了准确率高且运行速率快的数据筛选工具MobileNets，为串行晶体学实验提供有效便捷的数据筛选。”
        HUI Zi,YU Li,ZHOU Huan,TANG Lin,HE Jianhua
        Vol. 46, Issue 3, Article number: 030101(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030101
        摘要：BackgroundSerial X-ray crystallography has developed rapidly due to its advantages of data collection at room temperature, low radiation damage and time resolution. To solve protein structures by using the serial X-ray crystallography, a large amount of produced diffraction data needs to be screened for finding the effective diffraction patterns. The use of convolutional neural networks (CNN) can not only automate the data screening process, but also improve the accuracy of data classification comparing with the traditional "point finding method".PurposeThis study aims to explore five types of popular convolutional neural networks, i.e., AlexNet, GoogleNet, MobileNets, Vgg16, ResNet, for screening crystallographic diffraction patterns, and compare the accuracy and efficiency of them to build up a fast and accurate convolutional neural network tool for screening the diffraction patterns of different protein crystal samples.MethodsFirstly, the primitive data for model training extracted from the coherent X-ray image database, collected by Linac Coherent Light Source (LCLS) and Spring-8 Angstrom Compact free electron laser (SACLA), were pre-processed by gray level equalization and data enhancement. The deep learning models were trained by iteration of the preprocessed data. Then, the selected convolutional neural network through the comparison of accuracy and efficiency was used to process further the experimental data of protein crystals diffractions.ResultsThe results show that MobileNets not only has the accuracy similar to large networks such as ResNet, GoogleNet-Inception, but also runs faster.ConclusionsMobileNets provides an effective and convenient screening tool for serial X-ray crystallography experimental data.  
        关键词：Serial X-ray crystallography;Convolutional neural network;Machine learning;MobileNets   
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        发布时间：2024-10-25

        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • “在无损检测领域，快中子成像技术取得新进展。研究人员设计出一套裂变中子成像系统，直接视场达400mm×400mm，分辨率优于0.5mm，可检测尺寸不超过600mm的大型样品。”
        WANG Sheng,LI Hang,LUO Xin,WU Yang,HUO Heyong,LIU Bin,YIN Wei,CAO Chao,SUN Yong,YANG Xin,LI Rundong,TANG Bin
        Vol. 46, Issue 3, Article number: 030201(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030201
        摘要：BackgroundNeutron radiography (NR) is an important nondestructive testing method. NR is particularly useful for detection of light materials in medium and large heavy samples. Especially, the fast neutrons can penetrate the heavy materials and reveal the structure of the light materials. Compared to accelerator neutron sources, the fission neutrons elicited from a reactor are stable and of high quality. The fission neutron imaging is a useful complementary testing technology, especially for industrial applications that require high throughput and large-scale testing.PurposeThis study aims to investigate the super field of view neutron imaging by fission neutrons elicited from research reactor.MethodsBased on theoretical analysis and Monte-Carlo simulation, one filter combination was employed to improve the proportion of fission neutrons in the thermal neutron beamline at China Mianyang Research Reactor (CMRR). A fission neutron imaging system was constructed by employing a large field fast neutron fluorescent screen, short focus distance lens, and scientific charge coupled device (CCD) camera. Finally, some samples were tested using fission neutron tomography.ResultsThe fission neutron flux reaches up to 3×105 cm-2·s-1 when the L/D ratio is about 260. The field of view of NR is up to 400 mm×400 mm with resolution was better than 0.5 mm. Using super field of view method, samples less than 600 mm can be tested with this new system.ConclusionsCombination of theoretical calculation and experimental methods, fission neutron imaging can be improved to overcome some of the limitations of traditional neutron radiography techniques, and meet the needs of large sample detection in the future.  
        关键词：Research reactor;Neutron imaging;Fission neutrons;Super field of view   
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        发布时间：2024-10-25
      • “在核科学与核技术领域，专家设计了新型离子源，以提高同位素分离效率，满足市场需求。”
        WU Qi,LIU Yuguo,LIU Jianli,SUN Liangting,ZHAO Hongwei
        Vol. 46, Issue 3, Article number: 030202(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030202
        摘要：BackgroundStable isotopes play a crucial role in a variety of fields such as energy, military, semiconductor, agriculture, medicine, pharmacology, biology, food industry, and chemistry. With the rapid growth of nuclear science and technology applications in China, there has been an increasing demand for isotopes that cannot be met by current production capacities. Thus, the development of electromagnetic isotope separators capable of producing high yields and high isotopic purity has become necessary.PurposeThis study aims to develop an electromagnetic isotope separator based on a 2.45 GHz microwave ion source and isotopic magnet for studying a number of important heavy isotopes, such as xenon and molybdenum isotopes.MethodsFirstly, adjustable axial magnetic field in the source was designed by a double-solenoids to obtain high density plasma, and a high coupling efficiency matching waveguide was optimized by CST microwave computing module. Then. a crucible built in the discharge chamber was used to melt metal oxide for generating heavy metal ion beams. Finally, the discharge chamber, microwave coupling waveguides and heating oven of the ion source were simulated and designed for the generation of heavy ions.ResultsSimulation result shows that the temperature around the crucible is 917 ℃ when the current of heating wire is set to 70 A, and 100 mA hydrogen beam is generated during commissioning. The designed crucible in the discharge chamber can generate metal vapor efficiently for ionization, and achieve producing 20 emA Xe+ and 5 emA Mo+ respectively at the energy of 40 keV.ConclusionsThe feasible scheme of the magnetic field and microwave coupling design of this study are verified. The design of the 2.45 GHz electron cyclotron resonance (ECR) ion source provides a feasible and effective solution for the high yields isotope ions.  
        关键词：Electromagnetic mass separator;Isotope;Intense heavy ion beams;2.45 GHz microwave ion source   
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        发布时间：2024-10-25
      • “先进天基太阳天文台卫星的硬X射线成像仪量能器，采用IDE3381 ASIC，成功验证了其在空间辐射环境下的抗辐照性能。”
        WAN Qiang,GUO Jianhua,ZHANG Yan,ZHANG Yongqiang,HU Yiming
        Vol. 46, Issue 3, Article number: 030203(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030203
        摘要：BackgroundHard X-ray Imager (HXI) is one of the three scientific payloads onboard of the advanced space-based solar observatory (ASO-S). The calorimeter of HXI consists of 99 LaBr3 crystal and photomultiplier tube (PMT) detection units. A highly integrated charge-measurement application-specific integrated circuit (ASIC) with model IDE3381 is adopted in the front-end electronics of the calorimeter to process the signals from the 99 detection units on the space-limited and power-limited satellite platform.PurposeThis study aims to evaluate the radiation tolerance of model IDE3381 ASIC in a space radiation environment.MethodsA test bench with a flexible structure was designed by separating the device undergoing testing from the data acquisition (DAQ) system, hence shielding DAQ from the radiation environment. The performance of ASIC was automatically tested and monitored in the test bench during radiation tests. Both single-event effect (SEE), including single-event upset and single-event latch-up, and total ionizing dose (TID) tests were carried out by using a heavy ion beam and 60Co gamma-ray, respectively.ResultsThe test results show that the SEE threshold of model IDE3381 ASIC is greater than 75 MeV∙cm2∙mg-1, and the TID capacity is greater than 30 krad(Si).ConclusionsThe radiation tolerance of the charge measurement ASIC (model IDE 3381) meets the requirements of ASO-S HXI flight model.  
        关键词：Space electronics;Radiation effects;Application-specific integrated circuit (ASIC)   
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        发布时间：2024-10-25

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • “在纳米医学领域，研究人员成功制备了131I-BEV-PTX-SPIONs，并通过实验验证了其在肺癌诊疗中的潜力，为肿瘤靶向治疗提供了新思路。”
        JI Faquan,JI Anping,ZHANG Jie,BO Ling,JIAO Qingsong,QI Ning,ZHANG Dongsheng,DU Minghua
        Vol. 46, Issue 3, Article number: 030301(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030301
        摘要：Background131I-BEV-PTX-SPIONs is a type of nanoparticle used in cancer therapy. It is composed of four components: a radioactive isotope of iodine (131I), a chemotherapy drug called paclitaxel (PTX), a type of nanoparticle called superparamagnetic iron oxide nanoparticles (SPIONs), and a molecule called bevacizumab (BEV) which is an antibody that targets and blocks the growth of blood vessels that supply tumors.PurposeThis study aims to investigate the preparation and biological distribution of 131I-BEV-PTX-SPIONs.MethodsFirst of all, 131I-BEV-PTX-SPIONs were prepared, synthetized and identified. The transmission electron microscope (TEM) were employed to observe the particle characteristics. Then, 30 tumor-burdened nude mice were divided into the single targeting group and the dual targeting group for evaluation of 131I-BEV-PTX-SPIONs distribution in these nude mice, each group was divided into five sub-groups based on time points of 2 h, 6 h, 12 h, 24 h and 48 h, 3 in each sub-group. Finally, 131I-BEV-PTX-SPIONs were injected into the caudal vein of these mice, and experiments of biological distribution in vivo and SPECT imaging were carried out, and results were analyzed using GraphPad Prism 8.3 software.ResultsThe nanospheres in prepared 131I-BEV-PTX-SPIONs are obtained in good mono dispersion with a diameter of approximately 220 nm by TEM observation. 131I-BEV-PTX-SPIONs obtained in a high radiolabeling yield is about 81.4% with the radiochemical purity of over 99% and good stability shown in the 0.2 mol·L-1 PB buffer. And it could attain sustained PTX release in vitro. Comparing with the cellular uptake of 131I, a higher uptake and sustained PTX release in vitro are shown for 131I-BEV-PTX-SPIONs. Biodistribution experimental results show: After the injection of 131I-BEV-PTX-SPIONs, with the extension of time, the radiation count of the tumor is relatively higher, at 12 h reaching the peak. And the T/NT ratio increased gradually, and it reaches 7.8±0.50 at 48 h. The counts and the ratios at 6 h, 12 h, 24 h and 48 h are notably higher in the dual targeting group than the single targeting group (P<0.05), and over time the differences are more significant. SPECT examination results show: At 2 h after the injection of 131I-BEV-PTX-SPIONs, the tumor site has a radioactive build-up. With the extension of time, the accumulation of radioactivity increased and remained stable, and the T/NT ratio rises steadily.ConclusionsThese results demonstrated the potential of 131I-BEV-PTX-SPIONs in the diagnosis and treatment of lung cancer, and it was worthy of further study.  
        关键词：Superparamagnetic iron oxide nanoparticles;Paclitaxel;131I;Bevacizumab;Tumor bearing nude mice;Lung cancer   
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        发布时间：2024-10-25

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • “康普顿成像技术在核设施热点定位领域取得新进展，研制出双层分离式康普顿相机，实现了远场三维成像功能测试。该系统结构可调，成本低，成像视野宽，能量分辨率约为3%，能确定5米外137Cs点源三维位置信息，优化后的系统前锥角θ和侧向方位角φ的角分辨率约为10°。”
        WANG Wei,LI Xinglong,WU Jianhua,PANG Hongchao,LUO Zhiping
        Vol. 46, Issue 3, Article number: 030401(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030401
        摘要：BackgroundCompton imaging technology is a new radiation hotspot location technology that does not require collimation and has a wide field of view, high efficiency, and broad application prospects. With the development of nuclear technology, Compton cameras with the above-mentioned advantages have a wide range of applications not only in the nuclear industry but also in the field of nuclear medicine, hence recently become a popular research field worldwide.PurposeThis study aims to develop a double-layer separated Compton camera for far-field imaging of specific radiation scenes in nuclear facilities.MethodsFirst of all, two pixel-type cadmium zinc telluride (CZT) detectors and an application-specific integrated circuit (ASIC)-based readout electronics system were adopted for the development of a double-layer separated Compton camera. A list-mode maximum likelihood expectation maximization (LM-MLEM) image reconstruction algorithm was implemented in the host computer software. Then, 137Cs point source was used for experimental test of imaging performance of the system, and the parameters affecting the imaging performance, such as the detector layer spacing and area of the absorption layer, were optimized. Finally, far-field three-dimensional imaging of the radiation source was performed by moving the measuring position of the detector.ResultsThe test results show that the energy resolution of the CZT detectors is approximately 3% (FWHM@662 keV), which can determine the location of the point source at a distance of 5 m, and the angular resolution for θ and φ directions of the optimized system is approximately 10°.ConclusionsDouble-layer separated Compton camera of this study has advantages of adjustable structure, low detector cost, relatively simple readout electronics, and wide imaging field of view. The angular resolution of this double-layer separated Compton camera can be improved by proper adjustment of the imaging influence parameters (such as layer spacing and the area of the absorption layer).  
        关键词：Compton camera;Hot spot imaging;CdZnTe detector   
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        发布时间：2024-10-25
      • “在核电安全领域，国内研发的移动式微型裂变电离室中子探测器，其核特性与国外产品相当，有望实现国产替代。”
        YAN Jie,WEN Zhongwei,HE Yao,LIU Baili,HU Yonghong,WANG Mei,HAN Zijie,QIAN Dazhi
        Vol. 46, Issue 3, Article number: 030402(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030402
        摘要：BackgroundThe miniature fission ionization chamber is a widely used neutron detector for the in-core neutron flux monitoring of a nuclear reactor. Typically, the in-core neutron flux rate measurement system of a domestic CPR1000 nuclear power unit adopts a mobile miniature fission ionization chamber as the neutron probe to measure the neutron flux of the reactor and provide an in-core neutron flux distribution map during the operation. Therefore, it is an important piece of safety and control equipment for nuclear power plants.PurposeThis study aims to develope a mobile miniature fission ionization chamber neutron detector according to the service conditions and technical requirements of current foreign products.MethodsThe nuclear properties of self-made fission ionization chamber neutron detector was developed strictly following the national standard GB/T 7164-2022 and the industry standard NB/T 20215-2013. The gamma sensitivity was tested and compared with a reference commercial fission detector using a 60Co gamma source. The thermal neutron detection characteristic, including the length and slope of plateau, the thermal neutron sensitivity and linearity were tested in one test channel of the China Mianyang Research Reactor (CMRR) with neutron flux from 1×109 n∙cm-2∙s-1 to 4×1013 n∙cm-2∙s-1.Results & ConclusionsThe test results indicate that "domestic substitution" of this in-core safety product can be achieved, and the nuclear characteristics of self-developed prototypes are comparable to those of foreign products.  
        关键词：CPR1000;Mobile in-core detection system;Miniature fission ionization chamber;Neutron flux   
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        发布时间：2024-10-25
      • “在中子探测领域，自研塑料闪烁体取得重要进展。通过搭建探测系统，实现准确的γ射线能量标定，对比自研塑料闪烁体与商用塑料闪烁体EJ-299-33A的探测效率，为中子探测提供新选择。”
        SONG Yun,ZUO Jingxin,LIANG Yongfei,HAN Bing,BAI Lixin,YANG Chaowen
        Vol. 46, Issue 3, Article number: 030403(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030403
        摘要：BackgroundPlastic scintillators have potential for application in neutron detection. Two sizes (ø2.54 cm×2.54 cm, ø5.08 cm×5.08 cm) of plastic scintillators are self-developed by scientific research team in the school of physics, Sichuan University.PurposeThis study aims to experimental test the neutron/gamma (n-) discrimination performance for two self-developed plastic scintillators.MethodsA photomultiplier tube (PMT) was used to build detection systems, and high speed oscilloscope (LECROY HDO6104A) was employed to sample signal of detector for the energy calibration of the self-developed plastic scintillator. The pulse amplitude spectrum of 137Cs γ radiation source was measured and compared with the MCNP5 simulation spectrum to obtain the position information of the Compton edge and accurately calibrate the energies of γ rays. The data obtained from a 241Am-Be neutron source were analyzed using the charge integration method, and parameters such as the figure of merit (FOM), peak-to-valley ratio for neutrons, and the proportion of leaked neutrons over all neutron events were used to quantify the n-γ discrimination in different energy zones. The detection efficiencies of two self-developed plastic scintillators relative to the Commercial off-the-Shelf (COTS) EJ-299-33A were determined.ResultsThe results show that the FOM of ø2.54 cm×2.54 cm self-developed plastic scintillator is higher that of ø5.08 cm×5.08 cm self-developed plastic scintillator, and the detection efficiency of two self developed plastic scintillators relative to EJ-299-33A is about 0.49 and 1.0, respectively.ConclusionsThe performance of the ø5.08 cm×5.08 cm self-developed plastic scintillator is comparable to that of the COTS plastic scintillator EJ-299-33A with near the same discrimination ability.  
        关键词：Plastic scintillator;Energy calibration;n-γ;Discrimination ability quantification   
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        发布时间：2024-10-25

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • “在多核子转移反应领域，专家借助双核模型，系统研究了前平衡结团发射机制，为相关研究提供新思路。”
        XU Siyu,FENG Zhaoqing
        Vol. 46, Issue 3, Article number: 030501(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030501
        摘要：BackgroundThe pre-equilibrium cluster manifests the nuclear structure and reaction dynamics of collision system. The systematical investigation of cluster emission in transfer reactions is of significance in deep understanding of the synthesis of superheavy nuclei, shell evolution, new isotope production, etc.PurposeThe dynamics of pre-equilibrium cluster in a few of nucleon transfer reaction has been described by theoretical model, such as exciton model, cluster model. However, the cluster emission in massive transfer is very complicated because of the emission mechanism associated with the structure properties and also the dynamical process.MethodsIn this work, the pre-equilibrium cluster emission in massive transfer reaction has been systematically investigated within the dinuclear system model. The model has been successfully used for describing the massive fusion reaction and multi-nucleon transfer dynamics. The nucleon exchange and energy dissipation take place once the dinuclear system is formed. The nucleon transfer between the binary fragments is governed by the single-particle Hamiltonian and proceeds around the Fermi surface formed by the dinuclear system. The master equation is used for the nucleon transfer dynamics and the relative motion energy dissipation is taken into account. The dynamics of neutron, proton, deuteron, triton, 3He, 4He, 6,7Li and 8,9Be in collisions of 12C+209Bi, 40Ca+208Pb and 48Ca+238U near Coulomb barrier energies is analyzed, i.e., temporal evolution of production rate, kinetic energy spectra and angular distribution.ResultsIt is found that the emission probability of 4He is the same magnitude of proton emission and several orders larger than the one of 3He. Both the nuclear structure and dynamical effects influence the pre-equilibrium cluster production.ConclusionsThe pre-equilibrium clusters are emitted from the 'projectile-like' and 'target-like' fragments and the angular distributions manifest the similar trends. The kinetic energy spectra of clusters are shown as the Boltzmann distribution. The method is also extended to the cluster emission in weakly bound nuclei induced reactions by considering the preformation factor for the cluster construction.  
        关键词：Cluster emission;Pre-equilibrium process;Transfer reaction;Dinuclear system model   
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        发布时间：2024-10-25

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “在核反应堆模拟领域，研究人员开发了非结构网格核-热耦合程序MORPHY，通过TWIGL等基准题验证了其准确性和描述能力，为堆芯核热耦合分析提供新工具。”
        YANG Mingrui,SUN Qizheng,LUO Chixu,HE Donghao,LIU Xiaojing,ZHANG Tengfei
        Vol. 46, Issue 3, Article number: 030601(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030601
        摘要：BackgroundThere is usually a strong coupling of neutronics-thermal hydraulics (N-TH) fields inside nuclear reactors.PurposeThis study aims to accurately simulate the multi-physics fields in nuclear reactors by developing a three-dimensional N-TH coupling code MORPHY tailored to advanced complex reactors.MethodsFirst of all, a three-dimensional triangular-z nodal variational nodal method (VNM) was employed for neutronics calculation. and the stiffness confinement method (SCM) was used to solve the neutron temporal-spatial equation; thermal hydraulic calculations were based on the one-dimensional multi-channel model and the one-dimensional cylindrical thermal conductivity model. Then, the accuracy of neutron dynamics was verified by TWIGL benchmark, Dodds benchmark, and the typical pressurized water reactor (PWR) benchmark NEACRP. Finally, the effects of different coupling methods and angle discrete orders on the results were analyzed and compared against reference solutions by PARCS.ResultsVerification results of TWIGL benchmark show that the deviation of relative power from the reference results is less than 0.5%. Compared with the results of Dodds benchmark, it verifies the MORPHY code's ability to describe unstructured meshes. The transient coupling calculation capability of MORPHY is verified by NEACRP benchmark.ConclusionsNumerical solutions by MORPHY are in good agreement with reference results of the TWIGL, Dodds and NEACRP benchmark problems. It is concluded that MORPHY can adapt to the transient N-TH coupling analysis of nuclear reactor cores.  
        关键词：Neutron dynamics;Stiffness confinement method;Neutronics-thermal hydraulics coupling calculation;Transient;Transport code   
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      • “在中子活化计算领域，专家研发了一种高精度分析核素存量敏感性和不确定性的方法，为核设施辐射防护和源项分析提供工具和数据支持。”
        XIAO Yixin,ZHANG Jingyu,YU Xiao,ZHAO Xiaoze,TAN Lin,NI Wangmuhong,WANG Juanjuan
        Vol. 46, Issue 3, Article number: 030602(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030602
        摘要：BackgroundIn the neutron activation calculation, the inherent uncertainty of the input nuclear data will cause a certain impact on the calculation results. The uncertainty of the calculation results plays an important role in the source term analysis and radiation shielding design of nuclear facilities.PurposeThis study aims to analyze the uncertainty of neutron activation calculation based on direct derivative method.MethodsFirstly, the direct derivation method and Gear algorithm for uncertainty analysis were investigated, and the activation coefficient matrix and sensitivity coefficient matrix were constructed. Then, the Gear algorithm was employed to solve the activation equation and sensitivity equation simultaneously, and the sensitivity coefficient of nuclide inventory to nuclear data was obtained. The relative uncertainty of nuclide inventory was obtained by combining the relative uncertainty of nuclear data. Finally, This method was integrated into the neutron activation program ABURN, and typical examples was selected to test and verify its performance.ResultsThe calculation results of the nuclide inventory and its sensitivity coefficient and relative uncertainty by the ABURN program have little deviation from the analytical solution and the numerical solution of the European activation program FISPACT, most of the deviations do not exceed 0.2%, and the maximum deviation does not exceed 1%.ConclusionsVerification results show that the method and procedure developed in this paper have the ability to analyze the sensitivity and uncertainty of nuclide inventory with high precision, and can provide tools and data support for the radiation protection of nuclear facilities and the source term analysis.  
        关键词：Activation calculation;Uncertainty analysis;Direct derivation method;Gear algorithm;Sensitivity coefficient matrix   
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        发布时间：2024-10-25
      • “在核电站高温高压水环境中，注锌能有效抑制燃料包壳表面污垢沉积。随着锌浓度增加，污垢沉积厚度减小，内部镍铁比降低，硼析出量减少。当锌浓度达100μg⋅L^-1时，污垢内部有少量含锌物相析出。”
        LIAO Jiapeng,MAO Yulong,RUAN Tianming,HU Yousen,JIN Desheng,LI Jinggang,CHEN Zhongcun
        Vol. 46, Issue 3, Article number: 030603(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030603
        摘要：BackgroundUnder the condition of sub-cooled nucleate boiling (SNB), corrosion products in primary coolant of nuclear reactor will deposit on the outer surface of fuel cladding, which is commonly called fuel crud. Previous literature shown, zinc injection in primary coolant is an important method to inhibit the fuel crud deposition on the fuel cladding surface.PurposeThis study aims to investigate the influence of zinc concentration on the behavior of fuel crud deposition, and eventually provide guidance for zinc injection in primary coolant of nuclear power plant.MethodsThe fuel crud deposition tests of domestic zirconium alloy fuel cladding in different zinc concentrations were carried out by using a self-made fuel crud deposition device. Tubular crud deposition test specimen with built-in heating unit was designed and prepared for simulation study. After the tests, stereo microscope (SM) and scanning electron microscope (SEM) were employed to observe the macro and micro morphology of fuel crud whilst the composition of of fuel crud was observed and analyzed by the energy dispersive spectroscopy (EDS) with SEM, and X-ray photoelectron spectroscopy (XPS) was used to analyze the contents of Zn and B elements in the crud phase and inside the crud.ResultsObservation results show that the chimney-like crud formed on the fuel cladding surface becomes less obvious with increasing the zinc concentration in the coolant and the crud surface becomes flatter. Simutabeously, the crud thickness, the ratio of Ni/Fe and the boron precipitation mass within the crud are decreasing with increase of the zinc concentration. When the zinc concentration increases to 100 μg‧L-1, new Zn-containing phases precipitate within the crud.ConclusionsWithin the zinc concentration of 0~100 μg‧L-1, zinc injection in primary coolant of reactor can significantly inhibit the crud deposition on the fuel cladding surface.  
        关键词：Pressurized water reactor;Zirconium alloy cladding;Crud deposition;Boron precipitation;Zinc injection   
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        发布时间：2024-10-25
      • “据最新报道，美国橡树岭实验室的熔盐实验堆堆芯应急排盐系统失效概率为5.62×10-4，通过改进设计可降低失效概率，为液态熔盐堆安全运行提供参考。”
        LIANG Rongjian,SUN Liangjie,JIAO Xiaowei,WANG Chaoqun,YANG Qun,YU Xiaohan
        Vol. 46, Issue 3, Article number: 030604(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030604
        摘要：BackgroundCore fuel salt emergency drain system designed for fuel salt drain and afterheat removal, provides a safe shutdown mode for a molten salt reactor (MSR). It has important significance to evaluate reliability of the system for the safety of MSRs.PurposeThis study aims to quantitatively analyze the failure probabilty of the system and identify the pivotal factors that affecting the system failures, and provide suggestions for optimization of the system in engineering application.MethodsFirst of all, the fault tree analysis was employed to model the reliability of the core fuel salt drain system of MSRE through RiskSpectrum software. Then, the minimum cut sets and importance analysis was adopted to identify the most important basic event in fault tree of the system. Finally, two optimization methods, i.e., reduce the use of welds in bayonet cooling thimbles, and use different types of valves to isolate cooling gas flow of freeze valve, were proposed.ResultsThe results show that failure probability of the system is 5.62×10-4, and the identified pivotal factors affecting the system failures are welds leakage failures of thimbles and common cause failure of two groups valves of freeze valve. The optimization methods based on results of fault tree analysis can significantly reduce the system failure probability.ConclusionsThis study provides reference value for design and engineering application of the core fuel salt emergency drain system for MSRs.  
        关键词：System reliability;Molten salt reactor experiment;Core fuel salt emergency drain system;Fault tree;System optimization   
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      • “在核能和太阳能领域，熔盐传热储热性能研究取得新进展。专家设计了新型密封NMR样品池，可满足700℃熔盐体系检测需求，为熔盐微观结构研究提供新工具。”
        WU Huiyan,YINGSU Junheng,LIU Yiyang,HUANG Hailong,GE Min,QIAN Yuan,FU Xiaobin,LIU Hongtao
        Vol. 46, Issue 3, Article number: 030605(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030605
        摘要：BackgroundMolten salt systems have been extensively applied in the generation of nuclear and solar energy owing to their excellent heat transfer and storage performance. Therefore, it is essential to explore their physical and chemical properties, which are largely determined by their composition and ionic structure. In this regard, high-temperature (HT) nuclear magnetic resonance (NMR) has been demonstrated as an effective solution for qualitative analysis. Due to the existence of vent holes on the top of the commercialized standard NMR sample cell, it is not suitable for the study of some volatile, toxic or radioactive molten salt systems.PurposeThis study aims to implement ceramic NMR sample cells that are suitable for different molten salt systems.MethodsFirstly, a novel sealed sample cell that meets the requirements of molten salt systems was designed and produced by using an inner tube comprising AlN, BN, and Al2O3 ceramic materials, and an outer tube composed of ZrO2 ceramic materials. Then, with KBr as the standard sample, temperature calibration for this sample cell was conducted on the basis of 79Br NMR method. Finally, LiCl-KCl two-component molten salt (59.2 mol% LiCl-40.8 mol% KCl, eutectic melting point 353 ℃) was selected for HT-NMR experiment to verify the accuracy of temperature calibration, and check the performance of the HT-NMR method.ResultsExperimental results show that the sample cells are applicable in molten salt systems at a maximum temperature of 700 ℃, which meets the detection requirements of most molten salt systems. Additionally, the measurement results of the 79Br chemical shift of the KBr samples and captured HT 35Cl NMR spectra of the LiCl-KCl molten salt verify the reliability of the sample cell.ConclusionsBased on the results, the HT-NMR (High Temperature NMR) sample cells proposed in this study can be widely applied in various fields when the molten salt system requirements are met.  
        关键词：HT-NMR;Ionic structure of molten salts;NMR sample cells   
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        发布时间：2024-10-25
      • “在材料科学领域，专家通过粉末包埋渗铝工艺试验，分析了渗铝温度和保温时间对基体表面Fe-Al渗层的影响，并建立了动力学模型。”
        WANG Jun,LIU Chaonan,LIANG Chaofei,ZHANG Dongxun,WANG Zhenwei,ZHANG Jing,WANG Wei,JIANG Jinyao
        Vol. 46, Issue 3, Article number: 030606(2023) DOI: 10.11889/j.0253-3219.2023.hjs.46.030606
        摘要：BackgroundPack cementation aluminizing technology is a common method for preparing tritium barrier coatings, and its relative parameters during the preparation process have an important influence on the microstructure of the aluminide layer and the tritium barrier properties of the in-situ oxidized Al2O3 coating.PurposeThis study aims to investigate the effects of pack aluminizing conditions on the microstructure of the Fe-Al layer and analyze the related kinetic analysis of the aluminizing process.MethodsFirst of all, a pack aluminizing process activated by 1 wt% AlCl3 was used to fabricate aluminide coatings on the substrate of 316L stainless steel in the 923 K to 1 173 K range. Then, scanning electron microscope (SEM), energy dispersive spectrometer (EDS), and X-ray diffraction (XRD) were employed to characterize the cross-sectional microstructure and composition of the aluminized layer. Finally, the effects of aluminizing temperature and time on the microstructure and composition of the aluminized layer were analyzed, and the kinetic parameters of the formation of the Fe-Al layer and the relationship between aluminizing time and the thickness of the aluminized layer were further obtained.Results & ConclusionsThe experimental results show that the main phases of the aluminized layer are Fe2Al5 and FeAl with a certain amount of FeAl(Cr,Ni) precipitates. The high aluminizing temperature would accelerate the growth of aluminized layer and lead to the formation of a thick intermediate layer between the substrate and outer aluminized layer above 1 023 K. Simultaneously, extending the aluminizing time could increase the thickness of the Fe-Al layer, but has no effect on the phase composition. The relation between aluminizing temperature and the growth velocity of the Fe-Al layer is in accord with Arrhenius' equation, and the relative activation energy of the aluminizing process is about 79.23 kJ·mol-1. During the process of pack aluminizing, the relationship between the aluminizing time and the Fe-Al coating thickness is h=14.585t1/2+19.514.  
        关键词：Tritium permeation barrier;Pack aluminizing;Fe-Al layer;Catalysis;Diffusion kinetics   
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