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Research Papers

Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor

[+] Author and Article Information
Yao Xiao

Xi’an Jiaotong University,
Xi’an, Shaanxi, 710049, China;
Massachusetts Institute of Technology,
Cambridge, MA 02139
e-mail: yaoyuan.xiao@gmail.com

Lin-Wen Hu

Massachusetts Institute of Technology,
Cambridge, MA 02139
e-mail: lwhu@mit.edu

Suizheng Qiu

Xi’an Jiaotong University,
Xi’an, Shaanxi 710049, China
e-mail: szqiu@mai.xjtu.ed.cn

Dalin Zhang

Xi’an Jiaotong University,
Xi’an, Shaanxi 710049, China
e-mail: dlzhang@mai.xjtu.ed.cn

Su Guanghui

Xi’an Jiaotong University,
Xi’an, Shaanxi 710049, China
e-mail: ghsu@mai.xjtu.ed.cn

Wenxi Tian

Xi’an Jiaotong University,
Xi’an, Shaanxi 710049, China
e-mail: wxtian@mail.xjtu.ed.cn

1Corresponding author.

Manuscript received August 2, 2014; final manuscript received September 27, 2014; published online February 9, 2015. Assoc. Editor: Dmitry Paramonov.

ASME J of Nuclear Rad Sci 1(1), 011007 (Feb 09, 2015) (7 pages) Paper No: NERS-14-1031; doi: 10.1115/1.4026394 History: Received August 02, 2014; Accepted November 14, 2014; Online February 09, 2015

The fluoride-salt-cooled high-temperature reactor (FHR) is an advanced reactor concept that uses high-temperature tristructural isotropic (TRISO) fuel with a low-pressure liquid salt coolant. Design of the fluoride-salt-cooled high-temperature test reactor (FHTR) is a key step in the development of the FHR technology and is currently in progress both in China and the United States. An FHTR based on pebble-bed core design with a coolant temperature of 600–700°C is being planned for construction by the Chinese Academy of Sciences’ (CAS) Thorium Molten Salt Reactor (TMSR) Research Center, Shanghai Institute of Applied Physics (SINAP). This paper provides preliminary thermal-hydraulic transient analyses of an FHTR using SINAP’s pebble-bed core design as a reference case. A point kinetic model is implemented using computer code by coupling with a simplified porous medium heat transfer model in the core. The founded models and developed code are applied to analyze the safety characteristics of the FHTR by simulating several transient conditions including the unprotected loss of flow, unprotected overcooling, and unprotected transient overpower accidents. The results show that SINAP’s pebble-bed core is a very safe reactor design.

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References

Figures

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Fig. 1

TMSR-SF cross-sectional view

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Fig. 2

Model of TMSR-SF fuel pebble

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Fig. 3

Relative power and mass flow rate in the UOC accident

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Fig. 4

Temperatures in the UOC accident

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Fig. 5

Temperature reactivity feedback in the UOC accident

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Fig. 6

Relative power and flow in the UTOP accident

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Fig. 7

Temperatures in the UTOP accident

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Fig. 8

Temperature reactivity feedback in the UTOP accident

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Fig. 9

Relative power and flow in the ULOF accident

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Fig. 10

Temperatures in the ULOF accident

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Fig. 11

Temperature reactivity feedback in the ULOF accident

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