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

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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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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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