Phenomena identification and ranking table exercise for thorium based molten salt reactor-solid fuel design
Received date: 05 May 2018
Accepted date: 15 Sep 2018
Published date: 15 Dec 2019
Copyright
Thorium based molten salt reactor-solid fuel (TMSR-SF) design is an innovative reactor concept that uses high-temperature tristructural-isotropic (TRISO) fuel with a low-pressure liquid salt coolant. In anticipation of getting licensed applications for TMSR-SF in the future, it is necessary to fully understand the significant features and phenomena of TMSR-SF design, as well as its transient behavior during accidents. In this paper, the safety-relevant phenomena, importance, and knowledge base were assessed for the selected events and the transient of TMSR-SF during station blackout scenario is simulated based on RELAP/SCDAPSIM Mod 4.0.
The phenomena having significant impact but with limited knowledge of their history are core coolant bypass flows, outlet plenum flow distribution, and intermediate heat exchanger (IHX) over/under cooling transients. Some thermal hydraulic parameters during the station blackout scenario are also discussed.
Xiaojing LIU , Qi WANG , Zhaozhong HE , Kun CHEN , Xu CHENG . Phenomena identification and ranking table exercise for thorium based molten salt reactor-solid fuel design[J]. Frontiers in Energy, 2019 , 13(4) : 707 -714 . DOI: 10.1007/s11708-019-0616-0
1 |
Frepoli C. An overview of Westinghouse realistic large break LOCA evaluation model. Science and Technology of Nuclear Installations, 2008, 2008: 498737
|
2 |
Boyack B E, Catton I, Duffey R B, Griffith P, Katsma K R, Lellouche G S, Levy S, Rohatgi U S, Wilson G E, Wulff W, Zuber N. Quantifying reactor safety margins part 1: an overview of the code scaling, applicability, and uncertainty evaluation methodology. Nuclear Engineering and Design, 1990, 119(1): 1–15
|
3 |
Xu H, Dai Z, Cai X. Some physical issues of the thorium molten salt reactor nuclear energy system. Nuclear Physics News, 2014, 24(2): 24–30
|
4 |
Perez M, Allison C M, Wagner R J,
|
5 |
Scarlat R O, Laufer M R, Blandford E D, Zweibaum N, Krumwiede D L, Cisneros A T, Andreades C, Forsberg C W, Greenspan E, Hu L W, Peterson P F. Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology. Progress in Nuclear Energy, 2014, 77: 406–420
|
6 |
Xu H J. Thorium energy and molten salt reactor R&D in China. In: Revol J P, Bourquin M, Kadi Y, et al., eds. Thorium Energy for the World. Switzerland: Springer International Publishing Switzerland, 2016, 37–44
|
7 |
Liu L, Zhang D, Lu Q, Wang K, Qiu S. Preliminary neutronic and thermal-hydraulic analysis of a 2 MW thorium-based molten salt reactor with solid fuel. Progress in Nuclear Energy, 2016, 86: 1–10
|
8 |
Zhang D, Liu L, Liu M, Xu R, Gong C, Zhang J, Wang C, Qiu S, Su G. Review of conceptual design and fundamental research of molten salt reactors in China. International Journal of Energy Research, 2018, 42(5): 1834–1848
|
9 |
Ball S J. Next generation nuclear plant phenomena identification and ranking tables (PIRTs). Office of Scientific & Technical Information Technical Reports, Oak Ridge National Laboratory, US, 2008
|
10 |
Jiang S, Cheng M, Dai Z,
|
11 |
Jiang S, Cheng M, Dai Z,
|
12 |
Tian W, Qiu S, Su G, Jia D, Liu X, Zhang J. Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident. Annals of Nuclear Energy, 2007, 34(4): 288–296
|
/
〈 | 〉 |