核工程
热管
衰变热
中子输运
沸水堆
热工水力学
轻水反应堆
核反应堆堆芯
材料科学
管道
整体
沸腾
临界热流密度
传热
临界性
环境科学
传热系数
机械
核物理学
热力学
中子
工程类
化学
物理
生物化学
环境工程
催化作用
作者
Taiwo Saheed Yinusa,Huaping Mei,Chao Chen,Isaac Kwasi Baidoo,Shuyong Liu,Tao‐Sheng Li
出处
期刊:Kerntechnik
[De Gruyter]
日期:2024-12-18
标识
DOI:10.1515/kern-2024-0116
摘要
Abstract Various heat pipe-cooled reactors have been conceptualized and designed in recent years, ranging from kilowatts to megawatts, suitable for remote and extreme environments. However, existing designs employ monolith cores, which are saddled with heat transfer deteriorations due to thermal expansion and subsequent deformations are some of the key challenges facing monolith heat pipe reactors. Addressing this, a novel 300 kW heat pipe has been designed by introducing lead liquid instead of the monolith. A comprehensive Monte Carlo neutronics analysis of the designed core has been conducted including its thermal analysis. The core design comes with the following parameters: fresh core excess reactivity of 2.9914 $ that can support a 10-year life cycle, and a negative temperature coefficient of −0.1648 pcm/K. The axial and radial peak power factors at critical states were calculated to be 1.67 and 1.35 respectively. Preliminary thermal hydraulics analysis shows maximum temperatures of 1044 K under normal operation and worst-case accident scenarios (3 heat-pipe failures) of 1,149.9 K. These temperatures are lower than the melting point of uranium nitride fuel and lower than the possible heat pipe boiling failure limit at 1,300 K. Thus, the possibility of fuel melting/heat pipe boiling accidents is avoided. A hypothetical criticality accident was simulated, assuming the core was flooded with water, leading to an increased fission rate. However, the implementation of three emergency rods in the core ensures the subcritical of the reactor.
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