He Jishu/Nuclear Techniques

[Background] The 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 [Purpose] This 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 [Methods] Experts 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 and Conclusions] 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 © 2020, Science Press All right reserved

Y. Zhou

M. Dong

S. Sang

X. Liu

Nuclear Techniques

Guidance on quality control of nuclear medicine in Yangtze River Delta region during regular epidemic prevention and control period of the novel coronavirus pneumonia

长江三角洲地区新型冠状病毒肺炎常态化疫情防控期间核医学质量控制指南

In the early stage of the outbreak of COVD-19 in Wuhan city at the end of 2019, the demand for medical protective equipment increased rapidly Many problems emerged, such as poor quality and short supply of protective masks, shortage of medical supplies caused by long sterilization cycles, difficult treatment of the medical waste and wastewater of which might cause the secondary infection Herein, three specific applications of nuclear technology were summarized to fight against the COVID-19 The first one is the nuclear pore membrane (NPM) produced by nuclear technology It can be used to fabricate face masks with high filtration efficiency and good reusability after simple processing Hence the problems of poor reusability and poor filtration effects of common disposable masks can be solved by using NPM technology The second application is the radiation sterilization technology in the process of producing medical supplies such as masks and protective clothing The long cycle of common sterilization technology makes the demand exceed supply whereas the radiation sterilization technology can greatly shorten the production cycle and increase output, which could alleviate the shortage of medical supplies in anti-epidemic process The third application is the use of γ-ray, X-ray or high-energy electron to sterilize medical wastewater and garbage, among which massive of surviving coronavirus are still infectious It can treat large-volume of wastewater rapidly with a broad vision of application Due to these unique advantages, nuclear technology has been playing an important role in this epidemic prevention and control, it possesses broader development prospects in the future © 2020, Science Press All right reserved

Z. Wang

F. Lin

X. Sun

G. Ye

Y. Lu

Review of nuclear technology in the application of COVID-19 epidemic prevention and control

核技术在新冠肺炎疫情防控中的应用综述

新型冠状病毒肺炎疫情防控中核技术应用综述

新型冠状病毒肺炎常态化疫情防控期间长三角地区核医学质量控制指南

Abstract × Update Abstract English Chinese Update

核技术》编辑部 《

《核技术》新增4篇中国精品科技期刊顶尖论文(F5000)

[Background]As a new concept reactor,direct circulation CO2 cooled reactor has different system configurations and safety characteristics compared with direct cycle boiling water reactor,indirect cycle helium gas cooled reactor and pressurized water cooled reactor,hence the CO2 cooled reactor has different initial events and safety criteria.The selection of initial events is the foundation for the safety design of reactor whilst the safety criteria provides criterion for whether the safety analysis results meet the safety requirements.[Purpose]This study aims at the initial events and acceptance criteria for the safety design of CO2 cooled reactor.[Method]The main logic diagram analysis method was employed to study the initial events of the direct circulation CO2 cooled reactor.Based on the existing engineering experience of pressurized water reactor,gas cooled reactor,the acceptance criteria for the direct circulation CO2 cooled reactor were proposed according to its own characteristics.[Results&Conclusions]The proposed initial events and acceptance criteria required for safety analysis are applicable to direct circulation reactor,providing a basis for the safety analysis of CO2 cooled nuclear power plant,and gives an important reference for the safety design of direct cycle circulation reactors.

毛辉辉

张丹

高春天

吴攀

刘余

毕树茂

米争鹏

Study of initial events and safety criteria for CO2 cooled reactor

CO2冷却反应堆初始事件及安全准则研究

[Background]Assembly calculation plays an important role in reactor core design.The depletion calculation accuracy of the assembly calculation is of great significance to the power distribution,refueling life and reactivity control design of nuclear reactor core.[Purpose]This study aims to evaluate the accuracy of the multigroup constant library in the neutron depletion calculation and establish a set of depletion experimental calculation model.[Methods]The depletion historical parameters and the final nuclide composition information were provided by the SFCOMPO-2.0 database.The information of the Takahama-3 reactor,H.B.Robinson-2 reactor and Beznau-1 reactor samples were modeled using the DRAGON code.Some simplified methods were applied to some unavailable data information.The numerical results were compared and analyzed with the benchmark results in the SFCOMPO-2.0 database.[Result&Conclusions]The results show that most of the nuclide productions are in good agreement with the reference value,and the errors are within 10%.Nuclides with large differences between numerical results and benchmark results are discussed simultaneously,and computational results of three reactor samples were compared and analyzed.

汪天雄

张滕飞

吴海成

刘晓晶

熊进标

柴翔

Modeling and analysis of depletion experiment benchmark based on assembly calculation

基于组件计算的耗尽实验基准建模与分析

[Background] The new generation of pin-by-pin calculation method has gradually become the state-of-the-art approaches along with the improvement of computer technology and the development of core design. The difference between the pin-by-pin calculation and the traditional two-step scheme leads to the homogenization technique difficult to implement. [Purpose] This study aims to evaluate super homogenization techniques for pin-by-pin core calculation with emphasis on equivalent homogenization constants. [Methods] Super homogenization method was used as one of the main homogenization techniques of pin-by-pin calculation. For fuel assembly, the traditional super homogenization method was employed to generate the group constants. For reflector assembly with neutron leakage, the super homogenization method related to space leakage was applied to the generation of equivalent homogenization constant including super homogenization factor. [Results] Based on the threedimensional C5G7 benchmark, the application performance of the super homogenization method in pin-by-pin calculation is evaluated. The eigen-value relative error of pin-by-pin calculation is -0.001 6, assembly-power and pin-power relative errors are less than 5.5%. [Conclusions] Numerical results showed that the pin-by-pin calculations have the higher accuracy than the assembly-homogenized results.

张斌

李云召

吴宏春

Evaluation of super homogenization method for pin-by-pin core calculation

针对针棒堆芯计算的超均匀化方法评估

[Background]With the in-depth exploration of space,the power supply requirements for energy supply are gradually increasing.Space nuclear reactor power supply stands out in the deep space exploration mission due to its advantages of passivity,long life and high reliability,hence heat pipe nuclear reactor has become the focus of research in the field of space nuclear reactor.[Purpose]This study aims to evaluate the progress and technology of heat pipe space nuclear reactor used as power supply.[Method]First of all,the conceptual design of heatpipe reactor in the early stage and its application in Kilopower was summarized.Then the details of heatpipe power system(HPS),the heatpipe-operated mars exploration reactor(HOMER),safe affordable fission engine(SAFE)and Kilopower were investigated with emphasis on the structure design,fuel selection,heatpipe arrangement and power design of each reactor.[Results]This survey provides ideas and references for future research and design of heatpipe space nuclear reactor power system.[Conclusions]The design of heatpipe reactor is highly flexible and innovative.The use of different alkali metal heat pipes and thermoelectric conversion methods has a direct impact on the system power and the quality of the entire system.The combination of heat pipe and various thermoelectric conversion methods can be attempted.

ISSN	0253-3219
h-index	15

u9zg3I	物理化学量子力学材料科学工程类核物理学有机化学光学计算机科学生物复合材料电气工程数学冶金医学热力学色谱法地质学放射化学
+5d/bs	e+/GRg: Science China Press，uzYam8: ，dxwaWB: journal，8x2mMQ: Xn96QY
ak9yM6	A7IHrH: 1998，sQJ/D8: 0.00%，sE9og+:N.A.， wzlKC/: 0.00%
JrpmBe	16 weeks

He Jishu/Nuclear Techniques

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Guidance on quality control of nuclear medicine in Yangtze River Delta region during regular epidemic prevention and control period of the novel coronavirus pneumonia

Review of nuclear technology in the application of COVID-19 epidemic prevention and control

Guidance on quality control of nuclear medicine in Yangtze River Delta region during regular epidemic prevention and control period of the novel coronavirus pneumonia

Review of nuclear technology in the application of COVID-19 epidemic prevention and control

Guidance on quality control of nuclear medicine in Yangtze River Delta region during regular epidemic prevention and control period of the novel coronavirus pneumonia

《核技术》新增4篇中国精品科技期刊顶尖论文(F5000)

Study of initial events and safety criteria for CO2 cooled reactor

Modeling and analysis of depletion experiment benchmark based on assembly calculation

Evaluation of super homogenization method for pin-by-pin core calculation

A survey of heatpipe space nuclear reactor power supply

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xGGr6y	北大核心中国科学引文数据库中国科技核心期刊目录