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http://dx.doi.org/10.14346/JKOSOS.2022.37.4.129

Effect of Change of Reactor Coolant Injection Method on Risk at Loss of Coolant Accident due to Beam Tube Rupture  

Lee, Yoon-Hwan (Korea Atomic Energy Research Institute)
Lee, Byeonghee (Korea Atomic Energy Research Institute)
Jang, Seung-Cheol (Korea Atomic Energy Research Institute)
Publication Information
Journal of the Korean Society of Safety / v.37, no.4, 2022 , pp. 129-138 More about this Journal
Abstract
A new method for injecting cooling water into the Korean research reactor (KRR) in the event of beam tube rupture is proposed in this paper. Moreover, the research evaluates the risk to the reactor core in terms of core damage frequency (CDF). The proposed method maintains the cooling water in the chimney at a certain level in the tank to prevent nuclear fuel damage solely by gravitational coolant feeding from the emergency water supply system (EWSS). This technique does not require sump recirculation operations described in the current procedure for resolving beam tube accidents. The reduction in the risk to the core in the event of beam tube rupture that can be achieved by the proposed change in the cooling water injection design is quantified as follows. 1) The total CDF of the KRR for the proposed design change is approximately 4.17E-06/yr, which is 8.4% lower than the CDF of the current design (4.55E-06/yr). 2) The CDF for beam tube rupture is 7.10E-08/yr, which represents an 84.1% decrease compared with that of the current design (4.49E-07/yr). In addition to this quantitative reduction in risk, the modified cooling water injection design maintains a supply of pure coolant to the EWSS tank. This means that the reactor does not require decontamination after an accident. Thermal hydraulic analysis proves that the water level in the reactor pool does not cause damage to the nuclear fuel cladding after beam tube rupture. This is because the amount of water in the chimney can be regulated by the EWSS function. The EWSS supplies emergency water to the reactor core to compensate for the evaporation of coolant in the core, thus allowing water to cover the fuel assemblies in the reactor core over a sufficient amount of time.
Keywords
probabilistic safety assessment; core damage frequency; CDF; research reactor; beam tube rupture; loss of coolant accident;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
연도 인용수 순위
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