Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR)

被引:34
作者
Satvat, Nader [1 ]
Sarikurt, Fatih [1 ]
Johnson, Kevin [1 ]
Kolaja, Ian [1 ]
Fratoni, Massimiliano [1 ,2 ]
Haugh, Brandon [1 ]
Blandford, Edward [1 ]
机构
[1] Kairos Power LLC, 707 W Tower Ave, Alameda, CA 94501 USA
[2] Univ Calif Berkeley, Dept Nucl Engn, Berkeley, CA 94720 USA
关键词
D O I
10.1016/j.nucengdes.2021.111461
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
[No abstract available]
引用
收藏
页数:12
相关论文
共 50 条
[21]   A hybrid surrogate modeling framework for the Digital Twin of a Fluoride-salt-cooled High-temperature Reactor (FHR) [J].
Lim, Jasmin Y. ;
Li, Jin ;
O'Grady, Dan ;
Downar, Thomas ;
Duraisamy, Karthik .
NUCLEAR ENGINEERING AND DESIGN, 2025, 433
[22]   Performance evaluation of decay heat removal systems of Fluoride-salt-cooled High-temperature Reactor (FHR) [J].
Nakata, Junya ;
Ogura, Takahito ;
Miwa, Shuichiro ;
Mori, Michitsugu .
ANNALS OF NUCLEAR ENERGY, 2019, 133 :248-256
[23]   Dancoff factor analysis for pebble bed fluoride salt cooled high temperature reactor [J].
Qin, Wei ;
Yang, Kun ;
Chen, Jingen ;
Cai, Xiangzhou .
PROGRESS IN NUCLEAR ENERGY, 2016, 88 :332-339
[24]   NECP-panda: A neutronics and thermal-hydraulic analysis code for pebble-bed high temperature gas-cooled reactor [J].
Wu, Yuxuan ;
Wang, Yongping ;
Qin, Shuai ;
Cao, Liangzhi ;
Wu, Hongchun ;
Luo, Yong .
ANNALS OF NUCLEAR ENERGY, 2024, 208
[25]   Neutronics feasibility of an MIT Reactor-driven subcritical facility for the Fluoride-salt-cooled High-temperature Reactor [J].
Sun, Kaichao ;
Hu, Lin-wen ;
Forsberg, Charles .
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2017, 41 (14) :2248-2257
[26]   Sensitivity Analysis of an Overcooling Transient in the Generic Fluoride-Salt-Cooled High-Temperature Reactor [J].
Barthle, Jonathan L. ;
Lindsay, Isabelle O. ;
Satvat, Nader ;
Brown, Nicholas R. .
NUCLEAR SCIENCE AND ENGINEERING, 2025,
[27]   Development of the neutronics calculation module of neutronics and thermal hydraulic calculation program NECP-Panda for pebble-bed high temperature gas-cooled reactor [J].
Wu, Yuxuan ;
Wang, Yongping ;
Qin, Shuai ;
Cao, Liangzhi ;
Wu, Hongchun ;
Luo, Yong .
He Jishu/Nuclear Techniques, 2025, 48 (03)
[28]   Pore Scale Thermal Hydraulics Investigations of Molten Salt Cooled Pebble Bed High Temperature Reactor with BCC and FCC Configurations [J].
Song, Shixiong ;
Cai, Xiangzhou ;
Liu, Yafen ;
Wei, Quan ;
Guo, Wei .
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2014, 2014
[29]   Coupled neutronics–thermal-hydraulics analyses of unprotected transients in LBE-cooled Compact High-Temperature Reactor [J].
Dwivedi D.K. ;
Gupta A. ;
Kannan U. .
Life Cycle Reliability and Safety Engineering, 2023, 12 (3) :259-268
[30]   Sensitivity analysis and fuel performance of a control rod withdrawal in the generic fluoride-salt-cooled high temperature reactor [J].
Barthle, Jonathan L. ;
Bertrand, Bailey ;
Duchnowski, Edward M. ;
Wirth, Brian D. ;
Brown, Nicholas R. .
NUCLEAR ENGINEERING AND DESIGN, 2024, 428