中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings

文献类型:期刊论文

作者Sun, KC; Wilson, J; Hauptman, S; Ji, RM; Dave, AJ; Zou, Y; Hu, LW
刊名PROGRESS IN NUCLEAR ENERGY
出版日期2018
卷号109期号:-页码:171-179
ISSN号0149-1970
关键词REACTOR PACKING
DOI10.1016/j.pnucene.2018.08.005
文献子类期刊论文
英文摘要The first Solid Fueled Thorium Molten Salt Reactor (TMSR-SF1), a Fluoride-salt-cooled High Temperature Reactor (FHR) designed by the TMSR group of Chinese Academy of Science (CAS), is expected to be constructed in the near years. The combination of TRistructural-ISOtropic (TRISO) coated-fuel particles, pebble bed core, and Flibe coolant leads to various neutronics challenges, such as the double heterogeneity, distribution of TRISO particles, high density packed pebble bed, neutronics characteristics of Flibe salt, and etc. For the purpose of evaluating candidate neutronics codes, benchmark study will be conducted for the infinite fuel pebble lattice with explicitly described fuel particle distribution. For investigating key physics phenomena of the randomly packed pebble bed core, two coordinate generation methods will be explored in this study: Discrete Element Method (DEM) that accounts for inter-particle forces and a mathematical model (MM) that fills arbitrary do- mains through simple geometric rules on the addition of particles. While the former generates packing distributions closer to real-world scenarios, the latter is more computationally effective. The pebble loading effect on eigenvalues and fission power distribution will be studied. Emphasis is placed on the Flibe salt density reactivity effect - the most unique feature of the FHR comparing to the conventional High Temperature Gas-cooled Reactors (HTGRs). Neutron balance based reactivity decomposition method will be employed for describing the underlying physics.
语种英语
源URL[http://ir.sinap.ac.cn/handle/331007/31043]  
专题上海应用物理研究所_中科院上海应用物理研究所2011-2017年
作者单位1.MIT, 77 Massachusetts Ave, Cambridge, MA 02139 USA
2.Univ Chinese Acad Sci, Beijing 100049, Peoples R China
3.Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
推荐引用方式
GB/T 7714
Sun, KC,Wilson, J,Hauptman, S,et al. Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings[J]. PROGRESS IN NUCLEAR ENERGY,2018,109(-):171-179.
APA Sun, KC.,Wilson, J.,Hauptman, S.,Ji, RM.,Dave, AJ.,...&Hu, LW.(2018).Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings.PROGRESS IN NUCLEAR ENERGY,109(-),171-179.
MLA Sun, KC,et al."Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings".PROGRESS IN NUCLEAR ENERGY 109.-(2018):171-179.

入库方式: OAI收割

来源:上海应用物理研究所

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