Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor-Reference-Cited by-同舟云学术

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Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor

Published:2020-01-03 Issue:10 Volume:44 Page:8062-8073
ISSN:0363-907X
Container-title:International Journal of Energy Research
language:en
Short-container-title:Int J Energy Res

Author:

Peng Yu¹²^ORCID,Zhu Guifeng²^ORCID,Zou Yang²,Liu Sijia²,Xu Hongjie²

Affiliation:

1. Nanjing Institute of Technology Nanjing 211167 China

2. Shanghai Institute of Applied PhysicsChinese Academy of Sciences Shanghai 201800 China

Funder

Natural Science Foundation of Jiangsu Province

National Natural Science Foundation of China

Publisher

Wiley

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Link

https://onlinelibrary.wiley.com/doi/pdf/10.1002/er.5004

Reference26 articles.

1. Radioactive waste partitioning and transmutation within advanced fuel cycles: Achievements and challenges

2. Utilisation of thorium in reactors

3. Comparative analysis of high conversion achievable in thorium-fueled slightly modified CANDU and PWR reactors

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor;Annals of Nuclear Energy;2021-12

2. An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo;International Journal of Energy Research;2021-05-20

3. Spent fuel characteristics for thorium‐uranium recycle in fluoride‐salt‐cooled solid‐fuel fast reactor;International Journal of Energy Research;2021-03-04

4. Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies;International Journal of Energy Research;2020-11-23

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