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Volume 36 Issue 3
Feb.  2025
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Li Huaqi, Jiang Xinbiao, Yang Ning, Chen Lixin, hu Pan, Zhang Liang, Ma Tengyue, Zhu Lei. Transient Thermohydraulic Characteristics of HP-STMCs Space Reactor Core[J]. Nuclear Power Engineering, 2015, 36(3): 36-40. doi: 10.13832/j.jnpe.2015.03.0036
Citation: Li Huaqi, Jiang Xinbiao, Yang Ning, Chen Lixin, hu Pan, Zhang Liang, Ma Tengyue, Zhu Lei. Transient Thermohydraulic Characteristics of HP-STMCs Space Reactor Core[J]. Nuclear Power Engineering, 2015, 36(3): 36-40. doi: 10.13832/j.jnpe.2015.03.0036

Transient Thermohydraulic Characteristics of HP-STMCs Space Reactor Core

doi: 10.13832/j.jnpe.2015.03.0036
  • Received Date: 2014-07-14
  • Rev Recd Date: 2015-05-09
  • Available Online: 2025-02-15
  • The power transient model and reactivity feedback model on transient thermohydraulic characteristics analysis of Heat Pipe Segmeuted Thermoelectric Module Converters(HP-STMCs) cooled space reactorcore were built by using CFD interface UDF, and the HPSR core transient analysis code SNPS-FTASR was developed and approved with steady state calculation. The transient response of HP-STMCs core was studied on reactivity-insertion accident transient and a heat pipe failed transient. The results show that the power and UN temperature increased rapidly, then the power and temperature increased slowly to a final new steady state because of the core reactivity temperature feedback. The new power is 121.3% rated power. When a heat pipe failed, the UN fuel temperature increased rapidly and a great negative reactivity was brought to the core, thus the HP-STMCs core underwent a rapid power decrease and finally operated at 88.7% rated power. The maximum temperature of UN fuel increased by 140 K. It is approved by the result that the HP-STMCs core is safety at transient state including reactivity-insertion accident and a heat pipe failed.

     

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