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Design and optimization of passive residual heat removal system for lead-bismuth reactor SVBR-100
International Journal of Energy Research ( IF 4.3 ) Pub Date : 2020-11-08 , DOI: 10.1002/er.6139
Xinyu Li 1, 2 , Jie Cheng 1 , Dalin Zhang 2 , Zhiwen Dai 2
Affiliation  

The passive residual heat removal system (PRHRS) is of great significance to ensure the safety of small modular reactors. In this work, a PRHRS based on the reactor pressure vessel was designed and optimized for the lead-bismuth reactor SVBR-100 and an one-dimensional transient analysis code transient analysis codes for LBE reactor was developed as well. The uncertainty analysis was carried out to identify and optimize the key parameters affecting PRHRS, based on the one-dimensional physical fields obtained from the primary loop and evaporator. The results of transient calculation showed that the designed PRHRS can effectively remove the heat of the core under the accident of unprotected loss of flow and the station blackout (SBO). The results of sensitivity analysis showed that the maximum temperature of lead-bismuth eutectic (LBE) was strongly positively correlated with heat capacity and thermal conductivity of the cladding, and was moderately positively correlated with the kinetic coefficient of the pump; The medium negative correlation factor of peak pellet temperature (PPT), peak cladding temperature (PCT), and maximum LBE temperature was the diameter of the sleeve of PRHRS, and therefore, increasing the diameter of the sleeve can improve the performance of the system. The results of uncertainty quantification showed that the output uncertainties of PPT and PCT were larger than those inputs. The uncertainty of LBE temperature was very low, and all thermal parameters in SBO were within safe limits. Finally, the optimized parameters of PRHRS were obtained. This work can provide a reference for the development of designing PRHRS and relevant transient calculation codes for small modular LBE reactors.

中文翻译:

SVBR-100铅铋反应堆非能动余热排出系统设计与优化

被动余热排出系统(PRHRS)对于保障小型模块化反应堆的安全具有重要意义。在这项工作中,针对铅铋反应堆SVBR-100设计并优化了基于反应堆压力容器的PRHRS,并开发了LBE反应堆的一维瞬态分析程序瞬态分析程序。基于从主回路和蒸发器获得的一维物理场,进行不确定性分析以识别和优化影响 PRHRS 的关键参数。瞬态计算结果表明,所设计的PRHRS能够在无保护失流和停电事故(SBO)下有效去除堆芯热量。敏感性分析结果表明,铅铋共晶(LBE)的最高温度与包层的热容和热导率呈强正相关,与泵的动力学系数呈中度正相关;峰值颗粒温度(PPT)、峰值包层温度(PCT)和最大 LBE 温度的中等负相关因子是 PRHRS 的套筒直径,因此,增加套筒直径可以提高系统的性能。不确定度量化的结果表明,PPT 和 PCT 的输出不确定度大于那些输入。LBE 温度的不确定性非常低,SBO 中的所有热参数都在安全范围内。最后得到PRHRS的优化参数。
更新日期:2020-11-08
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