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Volume 42 Issue S2
Dec.  2021
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Zhong Ruicheng, Ma Yugao, Deng Jang, Liu Yu, Chai Xiaoming, Wang Jiageng. Reactor Startup Characteristics of Heat Pipe Cooled Reactor with Multiple Feedback Mechanism[J]. Nuclear Power Engineering, 2021, 42(S2): 104-108. doi: 10.13832/j.jnpe.2021.S2.0104
Citation: Zhong Ruicheng, Ma Yugao, Deng Jang, Liu Yu, Chai Xiaoming, Wang Jiageng. Reactor Startup Characteristics of Heat Pipe Cooled Reactor with Multiple Feedback Mechanism[J]. Nuclear Power Engineering, 2021, 42(S2): 104-108. doi: 10.13832/j.jnpe.2021.S2.0104

Reactor Startup Characteristics of Heat Pipe Cooled Reactor with Multiple Feedback Mechanism

doi: 10.13832/j.jnpe.2021.S2.0104
  • Received Date: 2021-07-19
  • Accepted Date: 2021-12-06
  • Rev Recd Date: 2021-11-10
  • Publish Date: 2021-12-29
  • The heat pipe-cooled reactor (HPR) has a high temperature solid core, so during the startup, it will experience large temperature rise and thermal expansion. Besides, the state of working fluid in the heat pipe will change, which would bring complex reactivity feedback. In order to study the startup characteristics of HPR under feedback mechanism, taking the megawatt HPR MegaPower designed by Los Alamos National Laboratory (LANL) as the research object, using the HPR transient analysis code HPRTRAN, the startup conditions of MegaPower are calculated with three startup modes, and the startup characteristics of each mode are studied. The results show that, relatively large power fluctuation occurs during the startup process of HPR, there may be a "temperature platform" that is not conducive to the startup, and that rotating control drum at intervals is a safer and more practical startup scheme than rotating control drum continuously.

     

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  • [1]
    余红星,马誉高,张卓华,等. 热管冷却反应堆的兴起和发展[J]. 核动力工程,2019, 40(4): 1-8.
    [2]
    MCCLURE P R, POSTON D I, DASARI V D, et al. Design of megawatt power level heat pipe reactors[R]. Los Alamos: Los Alamos National Laboratory, 2015.
    [3]
    YASIR ARAFAT, JURIE VAN WYK. eVinci Micro Reactor[J]. Nuclear Plant Journal, 2019: 34-37.
    [4]
    YAO C Z, HU G, XIE J C, et al. A scheme of lunar surface nuclear reactor power[J]. Science & Technology Review, 2015, 33(12): 19-23.
    [5]
    孙浩,王成龙,刘逍,等. 水下航行器微型核电源堆芯设计[J]. 原子能科学技术,2018, 52(4): 646-651. doi: 10.7538/yzk.2017.youxian.0465
    [6]
    马誉高,刘旻昀,余红星,等. 热管冷却反应堆核热力耦合研究[J]. 核动力工程,2020, 41(4): 191-196.
    [7]
    MA Y G, TIAN C Q, YU H X, et al. Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor[J]. Progress in Nuclear Energy, 2021, 140: 103904. doi: 10.1016/j.pnucene.2021.103904
    [8]
    马誉高,杨小燕,刘余,等. MW级热管冷却反应堆反馈特性及启堆过程研究[J]. 原子能科学技术,2021, 55(S2): 213-220.
    [9]
    郭志家,张金山,衣大勇,等. 空间核动力装置控制鼓系统试验样机热态性能试验[J]. 原子能科学技术,2019, 53(7): 1317-1323. doi: 10.7538/yzk.2018.youxian.0726
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