Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2015, Vol. 26 ›› Issue (2): 020601 doi: 10.13538/j.1001-8042/nst.26.020601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

No-core-melt assessment for Canadian-SCWR under LOCA/LOECC

WU Pan (吴攀),1 SHAN Jian-Qiang (单建强),1 GOU Jun-Li (苟军利),1, y ZHANG Bin (张斌),1 ZHANG Bo (张博),1 and WANG He-Nan (王贺南)1   

  1. 1School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China
  • Contact: GOU Jun-Li E-mail:junligou@mail.xjtu.edu.cn
  • Supported by:

    Supported by the Doctoral Program of Higher Education of China
    (No. 20120201110043) and Atomic Energy of Canada Limited(AECL)

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WU Pan, SHAN Jian-Qiang, GOU Jun-Li, ZHANG Bin, ZHANG Bo, and WANG He-Nan. No-core-melt assessment for Canadian-SCWR under LOCA/LOECC.Nuclear Science and Techniques, 2015, 26(2): 020601     doi: 10.13538/j.1001-8042/nst.26.020601

Abstract:

The safety analysis code SCTRAN for SCWR (Super CriticalWater Reactor) is modified to own the capability
to assess the radiation heat transfer with developing a two-dimensional heat conduction solution scheme and
incorporating a radiation heat transfer model. The verification of the developed radiation heat transfer model
is conducted through code-to-code comparison with CATHENA. The results show that the modified SCTRAN
code is successful for that the maximum absolute error and relative error of the surface temperature between
results of SCTRAN and CATHENA are 6:1 C and 0.9%, which are acceptable in temperature prediction. Then,
with the modified SCTRAN code, the loss of coolant accident with a total loss of emergency core cooling system
(LOCA/LOECC) of Canadian-SCWR is carried out to evaluate its “no-core-melt” concept. The following
conclusions are achieved: 1) in the process of LOCA, the decay heat can be totally removed by the radiation
heat transfer and the natural convection of the high-temperature coolant, even without an intervention of ECCS
(Emergency Core Cooling System); 2) The peak cladding temperature of the fuel pins in the inner and outer rings
of the high power group are 1236 C and 1177 C respectively, which are much lower than the melting point of
the fuel sheath. It indicates that the Canadian-SCWR can achieve “no-core-melt” concept under LOCA/LOECC.

Key words: Canadian-SCWR, LOCA/LOECC, No-Core-Melt, SCTRAN, Radiation heat transfer