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Phenomena identification and ranking table exercise for thorium based molten salt reactor-solid fuel design |
Xiaojing LIU1(), Qi WANG1, Zhaozhong HE2, Kun CHEN2, Xu CHENG1 |
1. School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China 2. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China |
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Abstract 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.
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Keywords
phenomena identification and ranking table (PIRT)
thorium based molten salt reactor-solid fuel (TMSR-SF)
safety analysis
RELAP/SCDAPSIM
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Corresponding Author(s):
Xiaojing LIU
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Online First Date: 12 March 2019
Issue Date: 26 December 2019
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1 |
C Frepoli. An overview of Westinghouse realistic large break LOCA evaluation model. Science and Technology of Nuclear Installations, 2008, 2008: 498737
https://doi.org/10.1155/2008/498737
|
2 |
B E Boyack, I Catton, R B Duffey, P Griffith, K R Katsma, G S Lellouche, S Levy, U S Rohatgi, G E Wilson , W Wulff , N Zuber. 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
https://doi.org/10.1016/0029-5493(90)90071-5
|
3 |
H Xu, Z Dai, X Cai. Some physical issues of the thorium molten salt reactor nuclear energy system. Nuclear Physics News, 2014, 24(2): 24–30
https://doi.org/10.1080/10619127.2014.910434
|
4 |
M Perez, C M Allison, R J Wagner, et al. The development of RELAP/SCDAPSIM/MOD 4.0 for advanced fluid systems design analysis. In: 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Gyeongju, South Korea, 2016
|
5 |
R O Scarlat, M R Laufer, E D Blandford, N Zweibaum, D L Krumwiede, A T Cisneros, C Andreades, C W Forsberg, E Greenspan, L W Hu, P F Peterson. Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology. Progress in Nuclear Energy, 2014, 77: 406–420
https://doi.org/10.1016/j.pnucene.2014.07.002
|
6 |
H J Xu. 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 |
L Liu, D Zhang, Q Lu, K Wang, S Qiu. 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
https://doi.org/10.1016/j.pnucene.2015.09.011
|
8 |
D Zhang, L Liu, M Liu, R Xu, C Gong, J Zhang, C Wang, S Qiu, G Su. Review of conceptual design and fundamental research of molten salt reactors in China. International Journal of Energy Research, 2018, 42(5): 1834–1848
https://doi.org/10.1002/er.3979
|
9 |
S J Ball. Next generation nuclear plant phenomena identification and ranking tables (PIRTs). Office of Scientific & Technical Information Technical Reports, Oak Ridge National Laboratory, US, 2008
|
10 |
S Jiang, M Cheng, Z Dai, et al. Extension and validation of RELAP/SCDAPSIM/MOD 4.0 code on FHR. Nuclear Power Engineering, 2016, 37(06): 33–36 (in Chinese)
|
11 |
S Jiang, M Cheng, Z Dai, et al. Preliminary steady state and transient analysis of a molten salt based reactor using RELAP/SCDAPSIM/MOD 4.0. In: 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2015), Chicago, US, 2015, 6130–6140
|
12 |
W Tian, S Qiu, G Su, D Jia, X Liu, J Zhang. Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident. Annals of Nuclear Energy, 2007, 34(4): 288–296
https://doi.org/10.1016/j.anucene.2007.01.010
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