Implementation of Leak Before Break (LBB) criteria in fast spectrum reactor

Sitangshu Sekhar Biswas , Soham Banerjee , S. Kudiyarasan , Sudip Ghosh , Prabhat Kumar
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Abstract

Sodium is employed as a coolant in the primary and secondary loops of fast reactors to transfer heat from the reactor and deliver it to the expander. However, handling sodium poses challenges and can be hazardous, as it reacts exothermically when exposed to air. Again, though there are radioactive barriers, there will be some radiation in the liquid coolant which makes it even more hazardous. Generally, P91 (9 % Cr and 1 % Mo) material is used in sodium-cooled nuclear reactors for its high-temperature strength, excellent creep resistance, and good corrosion and oxidation resistance, making it ideal for the demanding environment within the reactor and coolant line (Kudiyarasan and Biswas, 2024). Although, fast reactors operate at a lower pressure (1̴2 MPa) compared to the pressurized water reactors (5̴10 MPa), the operating temperature in the coolant line for fast reactors being very high (500 ֯ C̴800 ֯ C) unlike PWRs (̴300 ֯ C), there is a risk of brittle failure, due to factors such as material embrittlement from radiation exposure or stress concentrations, due to environmental interactions or a combination of different hydraulic transients (i.e. water hammering, thermal hammering or creep etc.) that can lead to sudden catastrophic failure under certain conditions. After thermal hammering, the main reason of hydraulic transients in fast spectrum reactor is found to be “Water Hammering”, which is nothing but sudden rise in pressure and propagation of pressure waves (shockwaves) resulting in high stress generation in the pipes. There are two primary reasons for “Water Hammering” i.e. i) Sudden closure or opening valves and ii) Due to sudden starting and stopping of pumps. In our paper, we have done numerical simulation on these hydraulic transient cases and found out the necessity to implement Griffith's criteria on designing the coolant line. Based on Griffith's LBB criteria and considering hydraulic transient scenario, we designed pipes for two different cases to find out the applicability of LBB criteria in transient case, experimentally and found out the criteria to be quite suitable to tackle this kind of problems in practical scenarios. Therefore, it seems obvious to always design the coolant line based on Griffith's criteria, so that leakage would occur before the complete failure takes place and this would give us ample time to successfully repair the coolant line before any catastrophic failure happens.
快谱反应堆先漏后破(LBB)准则的实现
在快堆的一次回路和二次回路中,钠被用作冷却剂,从反应堆传递热量并将其输送到膨胀器。然而,处理钠会带来挑战,而且可能是危险的,因为它暴露在空气中会发生放热反应。再一次,虽然有放射性屏障,但液体冷却剂中会有一些辐射,这使得它更加危险。通常,P91 (9% Cr和1% Mo)材料用于钠冷却核反应堆,因为它具有高温强度、优异的抗蠕变性能、良好的耐腐蚀性和抗氧化性,非常适合反应堆和冷却剂生产线内的苛刻环境(Kudiyarasan和Biswas, 2024)。虽然,与压水堆(5 - 10兆帕)相比,快堆在较低的压力下运行(1 - 2兆帕),但与压水堆(5 - 10兆帕)相比,快堆冷却剂管线的运行温度非常高(500 -֯C - 800 -֯C),与压水堆(300 -֯C)不同,由于辐射暴露或应力集中导致材料脆化等因素,由于环境相互作用或不同水力瞬态(即水锤击)的组合,存在脆性失效的风险。热锤击或蠕变等),在某些条件下可能导致突然的灾难性失效。经过热锤击后,发现快谱堆水力瞬变的主要原因是“水锤击”,即压力的突然升高和压力波(冲击波)的传播,导致管道内产生高应力。“水锤”有两个主要原因,即:1)阀门突然关闭或打开;2)泵突然启动和停止。本文对这些水力瞬变工况进行了数值模拟,得出了采用Griffith准则设计冷却液管线的必要性。基于Griffith的LBB准则,考虑水力瞬态情况,设计了两种不同情况下的管道,通过实验验证了LBB准则在瞬态情况下的适用性,并在实际情况下找到了非常适合解决这类问题的准则。因此,显然总是基于Griffith的标准来设计冷却剂管线,这样在完全失效之前就会发生泄漏,这将给我们足够的时间在任何灾难性故障发生之前成功修复冷却剂管线。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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