Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-14 DOI:10.1016/j.nucengdes.2025.113916
Vesa Riikonen, Virpi Kouhia, Markku Puustinen, Giteshkumar Patel, Antti Räsänen, Eetu Kotro, Juhani Hyvärinen
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Abstract

The presence of non-condensable gases in the reactor cooling system can significantly influence the operation of several safety systems within a nuclear power plant. The pressurized nitrogen volume at the top of the accumulator tank is the driving force for injecting accumulator water. In certain nuclear power plants, the release of gaseous nitrogen to the primary side is inhibited by an automatic closure of the accumulator injection line at the end of the discharge. However, if this automatic closure system fails, nitrogen will inadvertently flow into the reactor cooling system once the accumulators have been depleted. Furthermore, it is important also to note that the water within the accumulator is saturated with dissolved nitrogen, resulting in the injection of some nitrogen into the primary system alongside every accumulator discharge.
The impact of nitrogen on core cooling during loss of coolant accidents (LOCAs) has been investigated experimentally using the PWR PACTEL facility. The main observations were that when a break occurs in the hot leg, the injection of nitrogen from an accumulator can effectively prevent depressurization of the primary side. Consequently, the core can experience a heat-up at primary pressure somewhat above the typical low-pressure safety injection (LPSI) shut-off head. The decoupling of primary and secondary side pressures depends on the amount of nitrogen released from the accumulator, how much of it accumulates into the U-shaped steam generator heat exchange tubes, decreasing the condensation heat transfer, and the number of steam generators participating in the secondary side depressurization. Furthermore, the size of the break significantly affects the volume of nitrogen escaping through the break, which in turn influences the nitrogen levels within the system. Specifically, larger breaks permit a greater flow of nitrogen, thereby reducing the likelihood of disrupting heat transfer between the primary and secondary sides while also mitigating the depressurization of the primary side.
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按比例EPR模型热腿SBLOCA过程中氮气对堆芯冷却影响的实验研究
反应堆冷却系统中不凝性气体的存在会严重影响核电站内几个安全系统的运行。蓄能器罐顶的加压氮气体积是注入蓄能器水的动力。在某些核电站中,气体氮向一次侧的释放是通过在排放结束时自动关闭蓄能器注入管线来抑制的。然而,如果这个自动关闭系统发生故障,一旦蓄能器耗尽,氮气就会不经意地流入反应堆冷却系统。此外,还需要注意的是,蓄能器内的水已被溶解的氮饱和,导致每次蓄能器排放时都会向主系统注入一些氮。利用压水堆PACTEL装置对冷却剂损失事故(LOCAs)中氮对堆芯冷却的影响进行了实验研究。主要观察结果是,当热腿发生断裂时,从蓄能器注入氮气可以有效地防止一次侧的减压。因此,堆芯在主压力略高于典型的低压安全注入(LPSI)关闭水头时可能会经历升温。一次侧和二次侧压力的解耦取决于蓄能器释放的氮气量,其中有多少氮气积累到u型蒸汽发生器换热管中,减少冷凝换热,以及参与二次侧降压的蒸汽发生器数量。此外,裂口的大小显著影响通过裂口逸出的氮的体积,这反过来又影响系统内的氮水平。具体来说,更大的间隙允许更大的氮气流量,从而减少了破坏初级和次级侧之间传热的可能性,同时也减轻了初级侧的减压。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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