最新刊期
      卷 43 ， 期 9 ， 2020

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • “在同步辐射小角X射线散射技术领域，国内专家开发了PreSAXS1.0程序，实现了海量数据的快速处理。”
        LI Xiaoyun,LI Xiuhong
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090101
        摘要：BackgroundThe rapid development of small-angle scattering of X-ray (SAXS) has massively increased the speed of experiments to be performed and produced a large amount of raw data collected during each experiment. Although some software can available for batch processing, there are some difficulties in batch processing for deluged raw data, and there is no domestic batch processing available before.PurposeThis study aims to develop a package for single and batch processing to pre-analyze SAXS/WAXS patterns and the deluge data.MethodsBased on MATLAB platform, a semiautomatic data processing program PreSAXS 1.0 was implemented. It composed of four main capabilities: background subtraction, beam-center determination, sample-to-detector distance (SDD) calibration and the one-dimensional integrated intensity curves obtaining from deluged two-dimensional patterns. A comprehensive standard database was developed for fast indexing, and the circle fitting method was used to simulate the scattering/diffraction rings to find beam-center and calibrated SDD. The interpolation method from MATLAB was embedded in the package to improve the calculation speed.ResultsThe beamcentre find, SDD calibration, and I-q curves are perfectly appropriate to Irena, Raw software. After pre-data analysis, the data are saved as ASCII code and can be used for director read or further analysis by other software.ConclusionsPreSAXS 1.0 is easy to operate with user friendly interface, satisfies majority requirements of batch processing for SAXS data pre-analysis. However, PreSAXS 1.0 still needs to be improved, such as function extension, faster calculation speed and data analysis for GISAXS, etc.  
        关键词：Synchrotron radiation small angle of X-ray;Deluge data;Software;Batch processing   
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        发布时间：2024-10-25
      • “北京高能同步辐射光源项目中，轫致辐射吸收器能有效阻挡气体轫致辐射，但需采用铅和含硼聚乙烯组合屏蔽降低中子剂量当量率。”
        LIU Pingcheng,LIU Qiongyao,MA Zhongjian,ZHANG Huijie,YAN Mingyang,WANG Qingbin
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090102
        摘要：BackgroundThe high energy photon source (HEPS) currently under construction in Beijing will be the brightest synchrotron radiation facilities in the world. The high energy electrons which generate the desired synchrotron radiation interact with matter (for example, residual gas molecules in the vacuum chamber), to produce a spectrum of bremsstrahlung photons with energies up to the electron energy – in HEPS 6 GeV. The bremsstrahlung is highly penetrating, and it can produce exotic reactions in any material that it strikes, leading to the production of other radiations, especially photoneutrons. The beam stops are made of either lead or tungsten of rectangular shape in order to prevent the gas bremsstrahlung when transmitting through beamline to an experimental enclosure.PurposeThis study aims to design a new gas bremsstrahlung absorber to reduce the dose equivalent rate by simulation calculation based on the spectrum of scattered photons and photoneutrons for HEPS beamlines.MethodsBased on the technical specification, layout and related parameters of HEPS and the first optical enclosure (FOE), Monte Carlo simulation software FLUKA was mainly utilized to investigate the gas bremsstrahlung production in HEPS straight sections. A complete treatment of electron, positron and photon interactions at energies above 100 eV were calculated for the gas bremsstrahlung generated in the HEPS storage ring straight section and the gas bremsstrahlung transmitted through the beamline and scatters from components and the radiation emanating through the hutch wall.ResultsThe results show that the beam stop is effective in shielding photons, but the photoneutrons in HEPS beamlines is inevitable. The equivalent rate of neutrons outside the shield wall is still high. The maximum energy of neutrons in photonuclear reaction reaches upto 300 MeV. Giant resonance neutrons (0.1~5 MeV) account for 91% of the total flux of photoneutrons. Using polyethylene as local shield is a very effective method.ConclusionsThe combined shielding of lead and boron containing polyethylene can effectively reduce the neutron dose equivalent rate inside and outside FOE of HEPS beamlines.  
        关键词：Monte Carlo;Radiation shielding;Gas bremsstrahlung;HEPS   
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        发布时间：2024-10-25

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • “新冠疫情下，长三角核医学质控中心专家制定防控常态化核医学质控工作指导性意见，保障工作人员、患者及家属安全。”
        ZHOU Yujing,DONG Mengjie,SANG Shibiao,LIU Xuegong,LIU Xingdang
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090301
        摘要：BackgroundThe outbreak of corona virus disease (COVID-19) with a high risk of infection occurred in Wuhan city in December 2019, and gradually spread to other places. Current researches have shown that this atypical pneumonia is caused by a novel beta-coronavirus (βCoV), named severe acute respiratory syndrome coronavirus 2 (SARS-CoV-2). The population is generally susceptible to SARS-CoV-2, with an incubation period of 1~14 days, and the transmission routes include droplet transmission, contact transmission, and aerosol transmission. Since the outbreak of pneumonia in China, hospitals throughout the county have concentrated on the treatment of novel coronavirus pneumonia. As a result, routine clinics in hospitals at various levels have been affected. With the control of the epidemic situation in China, medical practice has been gradually restored and our country has entered the stage of regular epidemic prevention and control (EPC). Management of department of nuclear medicine faces new challenges in current regular EPC stage.PurposeThis study aims to comply with regular epidemic prevention and control of the novel coronavirus pneumonia and provide guidance for the doctors of nuclear medicine in Yangtze River Delta.MethodsExperts from the Yangtze River Delta region's nuclear medicine quality control center jointly formulated the guiding opinions on quality control of nuclear medicine in Yangtze River Delta region during regular epidemic prevention and control period of the novel coronavirus pneumonia, including in vivo and in vitro detection and ward treatment related to nuclear medicine. [Results andConclusions] Based on its diversity and particularity, the examinations related to nuclear medicine, higher requirements are put forward for nuclear medicine staff for prevention and control of the epidemic. Therefore, a guideline of quality control is needed to ensure the health and safety of the nuclear medicine staff, patients and their accompanying personnel.  
        关键词：Coronavirus infection;Nuclear medicine;Quality control;Guideline   
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        发布时间：2024-10-25
      • “在放疗定位领域，发泡胶对加速器剂量影响的研究取得新进展。专家利用蒙特卡罗程序建模计算，分析了不同厚度发泡胶对粒子剂量的影响，为临床使用提供参考。”
        XIAO Yang,ZHANG Qingxian
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090302
        摘要：BackgroundAt present, styrofoam is widely used in radiotherapy positioning, but there is no relevant report on its impact on accelerator basic dose.PurposeThis study aims to investigate the effects of different thicknesses of styrofoam on the particles dose of medical electronic linear accelerator flattening filter (FF) and flattening filter free (FFF) , and provide guidance for clinical use.MethodsThe Monte Carlo program EGSnrc was used for modeling and calculation. First of all, the PEGS4 material library and cross-section data were established according to the parameters of the styrofoam provided by the manufacturer, and the BEAMnrc was used to establish accelerator head models of different shooting fields of Varian True Beam series and perform calculations to generate corresponding phase space files. Then, the BEAMdp was employed to analyze the differences in ray energy spectrum and energy fluence generated by different model structures. Finally, the effect of different thickness foams on the fixed field and fixed thickness foams on the field was calculated and analyzed by using Dosexyznrc.ResultsIn the presence of styrofoam, the percentage depth dose (PDD) in both FF and FFF modes has a phenomenon of moving forward to varying degrees, resulting in an increase in the surface dose whilst little effect on the quality of the radiation. In the FF mode, the maximum dose deviation at the same depth is ≤2% when the thickness of the foam is ≤5 cm. When the thickness of the form reaches 10 cm, the maximum dose deviation at the same depth increases to 6%, and the PDD0 exceeds 90% in both modes. In both modes, the presence of styrofoam has a greater effect on the off-axis ratio and penumbra of the shot, the smaller the shooting field, the smaller the effect on the particle dose.ConclusionsWhen using styrofoam for clinical purposes, try to control the thickness within 5 cm, and FFF mode is recommended for more thicker styrofoam. Styrofoam has little effect on dose of stereotactic radiation therapy.  
        关键词：Styrofoam;Accelerator;Dose;Monte Carlo simulation   
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        发布时间：2024-10-25
      • “在硼中子俘获治疗领域，专家利用蒙特卡罗模拟设计了基于D-D中子源的BNCT慢化体，为中子通量探测器性能实验测试提供解决方案。”
        GONG Yi,GUAN Xingcai,WANG Qiang WANG Tieshan
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090303
        摘要：BackgroundBoron neutron capture therapy (BNCT) is a promising targeted cancer radiotherapy. The neutron source is pivotal to BNCT. The epithermal neutron flux is one of crucial characteristics for the BNCT neutron source. Therefore, in order to evaluate the quality of the BNCT neutron source, neutron flux detectors have been developed to measure the epithermal neutron flux accurately in our previous work.PurposeThis study aims to design a moderator for the D-D neutron source for evaluating the performances of the developed BNCT neutron flux detectors.MethodsThe MCNP5 (Monte Carlo N Particle Transport Code, version 5) was employed for the BNCT moderator design based on the D-D neutron source. First of all, the neutron spectrum of a D-D neutron source passing through a single-layer moderating material with different thickness was simulated. Then combined calculation was carried out for three moderator layers configured by different materials with various thickness.ResultsA suitable configuration of the BNCT moderator based on the D-D neutron source is obtained, that is, the combination of 5 cm thick polyethylene (PE) layer + 24 cm thick titanium trifluoride (TiF3) layer + 22 cm thick magnesium fluoride (MgF2) layer is adapted as the moderator material, 20 cm thick nickel (Ni) layer is employed as the reflector and 0.03 cm thick cadmium (Cd) sheet is used as the thermal neutron filter.ConclusionsThe moderated neutron beam can be used to evaluate the performances of the developed BNCT neutron flux detectors.  
        关键词：D-D neutron source;Moderator;BNCT;Monte Carlo simulation   
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        发布时间：2024-10-25

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • “在核电站棒控电源领域，专家分析电源电路，建立仿真模型，提出优化方法，有效改善高频振荡和电压过冲等问题，显著提高电路性能指标。”
        YANG Puqiong,ZHANG Jintao,WANG Xinlin,HE Zhengxi,ZHENG Gao
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090401
        摘要：BackgroundThe rod control power supply is the power supply for the driving mechanism of fuel rods in nuclear power plants (NPP). In the actual nuclear power plants, the rod control cabinet is usually far away from the driving mechanism and needs to be connected by a cable. In order to improve the integration of the equipment, many DC chopper modules in the bar control power supply cabinet share a rectifier module, but this design greatly increases the length of DC bus. The distributed inductance and distributed capacitance of the DC bus and cables will cause voltage overshoot, increase switching losses, and generate high-frequency oscillation, and cause great interference to power supply control.PurposeThis study aims to improve the performance of rod control power supply by circuit simulation and experimental verification.MethodsBased on the analysis of the power circuit, the distributed inductance of the DC bus and the distributed capacitance of the cable were calculated. Power simulation (PSIM) model of the rod-controlled power system was established, and the simulation results were compared with the prototype test waveforms. Then, an optimization method to reduce the distributed inductance of the DC bus was proposed. [Results andConclusions] After theoretical derivation and simulation verification, it can effectively improve the problems of high-frequency oscillation and voltage overshoot, and significantly improve the circuit performance indicators.  
        关键词：Rod control power supply;Distributed inductance;Distributed capacitance;Simulation;Optimization   
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        发布时间：2024-10-25
      • “在电源技术领域，专家提出了一种消除扫描电源输出电流过零畸变现象的技术方案，为提高电源输出电流线性度提供解决方案。”
        LU Huanting,LI Rui,WANG Chuanyun,WEI Jukui,WANG Zhen,CAO Yike
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090402
        摘要：BackgroundUsually, when the output current of the scanning power supply passes through zero, distortion will appear, which will affects the linearity of the output current.PurposeThis study aims to eliminate zero crossing distortion of output current of the scanning power supply by designing a novel scheme.MethodsThe working mode of the scanning power supply is designed as a continuous and zero-crossing inductance current. Firstly, the working mode of the power supply for the current zero-crossing distortion phenomenon was theoretically analysed, a smooth zero crossing solution under the current continuous mode (CCM) was able to achieve when combining switch H-bridge converter controlled by pulse width modulation (PWM) with the filtered inductance current and the reverse zero-crossing (RZC). Then the switching power supply simulation software “Simplis” was employed to study the power supply system working in the new mode. Finally, the prototype developed by this scheme was experimentally tested.ResultsThe simulation results show the rationality and effectiveness of the new scheme, and experimental results verify the realization of smooth zero crossing under CCM on the prototype.ConclusionsThe new scheme proposed in this study can effectively solve the zero-crossing distortion phenomenon of the output current of the scanning power supply.  
        关键词：Scanning power supply;H-bridge converter;CCM + RZC;PWM control   
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        发布时间：2024-10-25

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • “贵金属纳米材料局域表面等离子共振效应在纳米光子学等领域应用广泛，等离子体纳米探针在活细胞成像等方面具有优势。”
        LIU Wenhan,XIE Xiaodong,YIN Min,CHEN Nan
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090501
        摘要：Noble metal nanomaterials possess localized surface plasmon resonance (LSPR) effect. They are widely utilized in the fields of nanophotonics, chemical sensing, targeted radiation therapy, and bioimaging due to their unique physical, chemical, and optical properties. By adjusting the composition, morphology and size of the plasmonic nanoparticles, probes with distinct light scattering properties can be prepared and then monitored by dark-field microscopy (DFM). Compared with the fluorescent probes, plasmonic nanoprobes have better sensitivity and stability, which is suitable for live-cell imaging and real-time tracking of a single probe. Here, the latest development and some examples of plasmonic nanoprobes for dark-field imaging are introduced. Application in the observation of cell membrane receptors, in situ detection of intracellular biomolecules, and intracellular tracking are summarized, and perspects of plasmonic nanoprobes in DFM cell imaging are provided.  
        关键词：Plasmonic nanoprobes;Dark-field microscopy;Cell imaging;Single particle analysis   
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        发布时间：2024-10-25

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “阿尔及利亚比林核研究中心升级重水反应堆，实现不停堆连续辐照生产裂变钼，满足全球对放射性诊断核素99mTc的需求。”
        DING Li,ZHANG Aimin ZHANG Yi,ZHEN Jianxiao,GE Yanyan
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090601
        摘要：BackgroundIn order to meet the growing demand for diagnostic radionuclide 99mTc in the world, the Algeria Birine Nuclear Research Center launched the upgrade scheme of the multi-purposes heavy water research reactor (MHWRR), and put forward the need to establish continuous irradiation capacity of fission molybdenum. Limited by the existing infrastructure of the reactor, it is difficult to realize the loading/unloading and safe transportation of the target at the non-shutdown state of the reactor due to the high nuclear heat of the irradiated target.PurposeThis study aims to explore technical solution for continuous irradiation of fission molybdenum target in MHWRR.MethodsBased on the analysis and calculation of neutronic and thermal-hydraulic of the in-core targets, the thermal performance of the irradiated targets and the fission 99Mo yield during unloading after shutdown were calculated and analyzed. A technical solution that satisfied the yield requirements and production requirements of fission molybdenum was innovatively proposed by adopting short-period temporary shutdown. Implementation of the upgrading project was carried out after the proposal was accepted by the owner of MHWRR.Results & ConclusionsThe preliminary commissioning test results show that the theoretical values are in good agreement with the experimental values, indicating the irradiation scheme and process are reasonable and feasible.  
        关键词：MHWRR;Fission molybdenum;Target;Irradiation scheme   
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      • “在核能领域，研究者分析了U3-MA和U5-MA燃料装载模式在B&B快堆上嬗变MA的性能，为核废料处理提供新思路。”
        MA Yuwen,CHEN Jingen,YU Chenggang,WU Jianhui,LI Xiaoxiao
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090602
        摘要：BackgroundMinor actinides (MA) in the spent fuel is a significant contributor to long-term radiotoxicity. MA incineration is one of the effective ways for safe disposal of spent fuel. The small modular breed and burn (B&B) fast reactors have better neutron economy and longer lifetime, as well as the flexible and diverse loading mode. It can transmute long life nuclear waste and produce fissile fuel to solve the problems of the front-end nuclear fuel supply and the back-end spent fuel processing.PurposeThis study aims to analyse the incineration performance of MA fuel of a small modular B&B fast reactor (SM-B&B-FR).MethodsThe neutron properties of a SM-B&B-FR with e thermal power of 500 MWth, such as initial keff, spectra, burnup etc., were calculated by using the coupled code MOCBunup, MCNP and ORIGEN2. Fafety characteristics (delayed neutron fraction, temperature reactivity coefficient) and transmutation performance were analyzed to explore the effects on the reactor features at the same fuel element geometry with different initial MA loadings.ResultsThe results show that both loading strategies (U3-MA and U5-MA) achieve comparable incineration performance, and the transmutation capability shows a positive correlation to MA loading. The specific incineration consumption and incineration rate are 332.5 kg∙GWy-1, 86.1% for U3-MA, and 332.3 kg∙GWy-1, 87.2% for U5-MA which is superior to the transmutation ability of thermal reactor and comparable to ADS.ConclusionsThe addition of MA has a smaller effect on the delayed neutron fraction for Th-U fuel cycle compared to the U-Pu fuel cycle, but larger impact on the temperature reactivity coefficient. This study provides a possible approach to TRU nuclear waste minimization.  
        关键词：MA transmutation;Small modular B&B reactor;Fuel cycle   
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        发布时间：2024-10-25
      • “在熔盐自然循环特性研究领域，专家通过硝酸盐自然循环回路实验，验证了硝酸盐循环流量与换热功率的m次方成正比，为自然循环系统热工水力分析提供数据支持。”
        ZHANG Bo,XU Bo,ZHOU Chong,ZOU Yang,YU Xiaohan
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090603
        摘要：BackgroundNitrate natural circulation loop (NNCL) system is an important platform for studying molten salt natural circulation characteristics. The experimental data can be used to develop or validate thermal-hydraulic analysis codes.PurposeThis study aims to explore natural circulation characteristics of nitrate and verify the functional relationship of related parameters.MethodsDifferent experimental conditions were obtained by controlling the temperature of molten salt pool at 310, 340, 370 centigrade and the opening of air cooling tower throttle at 0%, 25%, 50%, 75%, 100%. Both the transient and steady state characteristics were observed. Combining theoretical analysis and experimental data, the analytical solution was obtained by the method of fitting approximation.ResultsThe response time of the temperature difference of the DRACS heat exchanger (DHX) to the temperature change of molten salt pool is more than 20 h, and the response time to the wind speed change is several minutes. The natural circulation flow rate of nitrate in the NNCL system is proportional to the m-th power of DHX heat exchange power, and the resistance of the NNCL system is proportional to the (1-m)/m-th power of the flow; the m value of the NNCL system is between 0.47~0.49.ConclusionsThe relationship between the natural circulation flow-power of the DHX and the natural circulation pressure drop-flow is well verified by the experimental results.  
        关键词：Natural circulation;Nitrate;Thermal hydraulic   
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      • “在核电厂事故分析领域，专家构建了气溶胶水洗计算模型，探究气泡尺寸对净化效果的影响，为事故源项评估提供新思路。”
        LI Yuxiang,ZHOU Yan,TONG Lili
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090604
        摘要：BackgroundAerosol pool scrubbing is an important part of the radioactive source term analysis under severe accidents in nuclear power plants.PurposeThis study aims at the determination of bubble size which is critical for the reasonable evaluation of aerosol removal efficiency due to pool scrubbing.MethodsFirst of all, the calculation model of aerosol pool scrubbing was established, and the correlation of average bubble size was applied to predict the uniform size of stable bubble swarm in the rise zone. Then the influence of bubble size on the decontamination factor (DF) calculation of aerosol pool scrubbing was investigated by simulating the typical conditions of LACE-Espana and ACE experiments with different injection devices.Results & ConclusionsThe comparison results show that calculated DFs using the bubble diameter predicted by Akita’s correlation are closer to the experimental data, and the DF increases with the decrease of bubble size.  
        关键词：Bubble size;Multi-hole;Aerosol pool scrubbing;Decontamination factor   
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      • “在高温钠环境中，硅酸钙绝热材料表现出良好的抗腐蚀性能，为核反应堆安全运行提供保障。”
        ZHANG Jinquan,XU Yongli,LONG Bin
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090605
        摘要：BackgroundCalcium silicate products were used as thermal insulation for China Experimental Fast Reactor (CEFR) cock, which might in contact with sodium vapor and liquid sodium.PurposeThis study aims to investigate the compatibility of calcium silicate thermal insulation with sodium and sodium vapor.MethodsFirst of all, gloves box purified by argon circulating and static testing facility of high temperature sodium were employed to build a test platform. The tests of the compatibility of calcium silicate insulation with high temperature sodium vapor and sodium at 250 ℃ for duration ranges from 3 min to 1 500 h. After the test, some examinations include surface morphology analysis, cross section morphology analysis and thermal conductivity were performed.ResultsThe results show that there is no fierce reaction occurred between calcium silicate insulation with sodium and sodium vapor. Varitions of color and appearance only appear on the surface of the samples, not inside the sample. During the fabrication process of the insulation post-test, the samples do not become brittle or soft. The thermal conductivity of the samples remains constant before and after the test, sodium and sodium vapor have no effect on the thermal insulation property of samples.ConclusionsThe calcium silicate has good resistance to sodium and sodium vapor corrosion.  
        关键词：Fast reactor;Calcium silicate insulation;Compatibility;Sodium corrosion   
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      • “在核反应堆安全领域，专家采用RELAP5-TMSR程序，分析了紧急停堆棒落棒时间对熔盐堆反应性引入瞬态后果的影响，为熔盐堆安全运行提供解决方案。”
        WANG Kai,JIAO Xiaowei,YANG Qun,WU Yanhua WANG Chaoqun,HE Zhaozhong
        Vol. 43, Issue 9, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.090606
        摘要：BackgroundThe scram rod drop time is an important parameter for reactor safety analysis, which is of great significance to the safety of molten salt reactor (MSR). The process and the consequences of the design basis events of the MSR will be significantly influenced by the dropping time of scram rod.PurposeThis study aims to analyse the effect of the scram rod drop time on the consequences of MSR reactivity insertion transient.MethodsFirst of all, the RELAP-MS based RELAP5-TMSR (reactor excursion and leak analysis program-thorium molten salt reactor) code was employed to establish the safety analysis model for the transient simulation of TMSR-LF. Then, the sensitivity of control rod withdrawal speed to transient consequences was analyzed, next, reactivity introduction event caused by the withdrawal of a control rod at full power was taken into account to analyse the vartions of power, temperatures of fuel salt and structure materials. Influence of scram rod dropping time in emergency shutdown on transient consequences of reactivity introduction in MSR was analyzed.ResultsEven if the scram rod drop time reaches as long as 10 min, the maximum temperature of Harrington alloy is 708.2 °C, and the maximum temperature of fuel salt is 709.2 °C, which is below the safety limit.ConclusionsThe molten salt reactor has good safety characteristics, low requirements for scram rod drop time, and the ability to deal with reactivity insertion event.  
        关键词：Molten salt reactor;Scram rod drop time;RELAP-TMSR;Safety analysis   
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