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NEUTRONICS: 作品数：41被引量：37H指数：3; 导出分析报告; 相关领域：理学更多>>; 相关作者：李林森更多>>; 相关机构：清华大学更多>>; 相关期刊：《World Journal of Nuclear Science and Technology》《Annual Report of China Institute of Atomic Energy》《Frontiers in Energy》《Southwestern Institute of Physics Annual Report》更多>>; 相关基金：国家自然科学基金中国博士后科学基金安徽省自然科学基金更多>>

An improved analysis method for assessing the nuclear-heating impact on the stability of toroidal field magnets in fusion reactors: 《Nuclear Science and Techniques》2024年第6期163-176,共14页Yu-Dong Lu Jin-Xing Zheng Xu-Feng Liu Huan Wu Jian Ge Kun Xu Ming Li Hai-Yang Liu Lei Zhu Fei Liu; the National Natural Science Foundation of China(Nos.52222701,52077211,and 52307034).; The superconducting magnet system of a fusion reactor plays a vital role in plasma confinement,a process that can be dis-rupted by various operational factors.A critical parameter for evaluating the temperature margin...; 关键词：Superconducting magnet Nuclear heating NEUTRONICS Thermal hydraulics

Preliminary safety analysis for heavy water-moderated molten salt reactor: 《Nuclear Science and Techniques》2024年第6期202-217,共16页Gao-Ang Wen Jian-Hui Wu Chun-Yan Zou Xiang-Zhou Cai Jin-Gen Chen Man Bao; the National Natural Science Foundation of China(No.11905285);the Shanghai Natural Science Foundation(No.20ZR1468700);the Youth Innovation Promotion Association CAS(No.2022258).; The heavy water-moderated molten salt reactor(HWMSR)is a newly proposed reactor concept,in which heavy water is adopted as the moderator and molten salt dissolved with fissile and fertile elements is used as the fuel....; 关键词：Heavy water-moderated molten salt reactor Neutronics and thermal-hydraulics coupling Transient analysis Accident analysis

Physics design of 14 MeV neutron generator facility at the Institute for Plasma Research: 《Plasma Science and Technology》2023年第12期115-121,共7页H L SWAMI S VALA M RAJPUT M ABHANGI Ratnesh KUMAR A SAXENA Rajesh KUMAR; A high energy and high yield neutron source is a prime requirement for technological studies related to fusion reactor development. It provides a high-energy neutron environment for small-scale fusion reactor componen...; 关键词：neutron generator NEUTRONICS ACCELERATOR physics design nuclear fusion

Evaluating the JEFF 3.1, ENDF/B‑VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel被引量：4: 《Nuclear Science and Techniques》2022年第12期173-189,共17页Cici Wulandari Abdul Waris Sidik Permana Syeilendra Pramuditya; This study evaluated the nuclear data libraries for a small 100 Mega Watt electric(MWe)Molten Salt Reactor with plutonium fuel.The reactor has a power output of 100 MWe,which meets the demand for electricity generatio...; 关键词：NEUTRONICS PLUTONIUM Small MSR THORIUM SRAC

Implementation of high-fidelity neutronics and thermal–hydraulic coupling calculations in HNET被引量：3: 《Nuclear Science and Techniques》2022年第11期120-132,共13页Yan-Ling Zhu Xing-Wu Chen Chen Hao Yi-Zhen Wang Yun-Lin Xu; supported by the China Postdoctoral Science Foundation(No.2021M703045);the National Natural Science Foundation of China(No.12075067);the National Key R&D Program of China(No.2018YFE0180900).; To perform nuclear reactor simulations in a more realistic manner,the coupling scheme between neutronics and thermal-hydraulics was implemented in the HNET program for both steady-state and transient conditions.For si...; 关键词：Coupling calculation High-fidelity neutronics THERMAL-HYDRAULICS Matrix-free Newton/Krylov method Transient simulation

Flow field effect of delayed neutron precursors in liquid-fueled molten salt reactors被引量：3: 《Nuclear Science and Techniques》2022年第8期16-32,共17页Xian-Di Zuo Mao-Song Cheng Yu-Qing Dai Kai-Cheng Yu Zhi-Min Dai; supported by Strategic Pilot Science and Technology Project of Chinese Academy of Sciences (No. XD02001005); In molten salt reactors(MSRs),the liquid fuel salt circulates through the primary loop and a part of the delayed neutron precursors(DNPs)decays outside the reactor core.To model and analyze the flow field effect of DN...; 关键词：Molten salt reactor Delayed neutron precursor Nodal expansion method Coupled neutronics and thermal-hydraulics

Application of local Monte Carlo method in neutronics calculation of EAST radial neutron camera被引量：1: 《Plasma Science and Technology》2022年第2期172-179,共8页Liangsheng HUANG Liqun HU Luying NIU Mengjie ZHOU Bing HONG Kai LI Ruixue ZHANG Guoqiang ZHONG; support and help in this research.This work was supported by Users with Excellence Program of Hefei Science Center CAS(No.2020HSC-UE012);Comprehensive Research Facility for Fusion Technology Program of China(No.2018-000052-73-01-001228);National Natural Science Foundation of China(No.11605241)。; The Local Monte Carlo(LMC)method is used to solve the problems of deep penetration and long time in the neutronics calculation of the radial neutron camera(RNC)diagnostic system on the experimental advanced supercondu...; 关键词：equivalent surface source radial neutron camera EAST local Monte Carlo method

Core designing of a new type of TVS-2M FAs:neutronics and thermal-hydraulics design basis limits: 《Frontiers in Energy》2021年第1期256-278,共23页Saeed GHAEMI Farshad FAGHIHI; Sincere thanks are due to the Shiraz University Research Council for his financial support.; One of the most important aims of this study is to improve the core of the current VVER reactors to achieve more burn-up(or more cycle length)and more intrinsic safety.It is an independent study on the Russian new pro...; 关键词：TVS-2M FAs core design basis limits VVER-1000 analysis mixture of uranium-gadolinium oxides fuels THERMAL-HYDRAULICS PARCS WIMS-D5

Neutronics analysis for MSR cell with different fuel salt channel geometries被引量：4: 《Nuclear Science and Techniques》2021年第1期75-84,共10页Shi-He Yu Ya-Fen Liu Pu Yang Rui-Min Ji Gui-Feng Zhu Bo Zhou Xu-Zhong Kang Rui Yan Yang Zou Ye Dai; This work was supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000);the Frontier Science Key Program of Chinese Academy of Sciences(No.QYZDYSSW-JSC016);the Shanghai Sailing Program(No.Y931021031).; The neutronic properties of molten salt reactors(MSRs)differ from those of traditional solid fuel reactors owing to their nuclear fuel particularity.Based on the Monte-Carlo N particle transport code,the effects of th...; 关键词：Molten salt reactor Fuel salt channel Cell geometry NEUTRONICS

Simulation of a molten salt fast reactor using the COMSOL Multiphysics software被引量：1: 《Nuclear Science and Techniques》2020年第12期1-19,共19页D.H.Daher M.Kotb A.M.Khalaf Moustafa S.El-Koliel Abdelfattah Y.Soliman; In this study,COMSOL v5.2 Multiphysics software was utilized to perform coupled neutronics and thermal–hydraulics simulations of a molten salt fast reactor,and the SCALE v6.1 code package was utilized to generate the...; 关键词：Molten salt COMSOL SCALE NEUTRONICS THERMAL-HYDRAULIC

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