首页> 外文会议>International topical meeting on probabilistic safety assessment and analysis >LOVIISA NPP PRESSURIZED THERMAL SHOCK (PTS) THERMAL HYDRAULIC ANALYSES USING APROS SIMULATION CODE
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LOVIISA NPP PRESSURIZED THERMAL SHOCK (PTS) THERMAL HYDRAULIC ANALYSES USING APROS SIMULATION CODE

机译:使用APROS仿真代码,Loviisa NPP加压热冲击(PTS)热液压分析

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Loviisa Nuclear Power Plant consists of two WER-440 type pressurized water reactor units and it is owned by a Finnish energy company Fortum Power and Heat Oy. Only some years after Loviisa Unit 1 start-up, during early 1980's, some reactor pressure vessel embrittlement by fast neutron irradiation was recognized. Embrittlement of the reactor pressure vessel materials increases the risk of a fast fracture under emergency core cooling conditions. This lead to an extensive study of pressurized thermal shock (PTS) scenarios, which included experimental research, large set of probabilistic and deterministic safety analyses, code development and plant modifications to both lower overcooling transient probability and to mitigate it's consequences. Operating licenses for Loviisa 1 and 2 Units reactor pressure vessels have now been applied by Fortum to cover operation up to the years 2027 and 2030, respectively. Operating licenses were granted as applied by the Finnish Radiation and Nuclear Safety Authority (STUK) according to application. However a constant know-how of PTS scenarios will be maintained. PTS-scenario related thermal hydraulic analyses are based on the original 80's decade analyses. The most important cases were recalculated using Apros (Advanced Process Simulator) because numerous plant modifications were changed the boundary conditions needed in the analyses. Probabilistic safety analyses included totally over 160 different PTS-sequences. The most limiting sequences were selected for deterministic analyses. PTS-analyses were performed in co-operation with Platom Oy and plant owner Fortum Power and Heat Oy. The main results of PTS-analyses are presented in the paper.
机译:Loviisa核电站由两个WER-440型加压水反应堆单元组成,它由芬兰能源公司Fortum Power和Heat Oy拥有。在Loviisa单位1次启动后,只有几年,在20世纪80年代初,识别出快速中子辐射的一些反应堆压力容器脆化。反应器压力容器材料的脆化增加了紧急核心冷却条件下快速骨折的风险。这导致对加压热冲击(PTS)情景进行了广泛的研究,包括实验研究,大量概率和确定性安全分析,代码开发和植物修改,既较低过冷瞬态概率,也会减轻其后果。 Loviisa 1和2个单位的操作许可证现在已经通过Fortum施加了难以分别涵盖2027和2030的操作。根据申请,芬兰辐射和核安全管理局(Stuk)所应用的经营许可证。然而,将保持持续的PTS方案的持续诀窍。 PTS-Scenario相关的热液压分析基于原始的80年代十年分析。使用APROS(高级过程模拟器)重新计算最重要的情况,因为众多植物修改都改变了分析所需的边界条件。概率安全分析包括完全超过160种不同的PTS序列。选择最有限的序列用于确定性分析。 PTS分析在与镀坡和植物所有者Fortum电源和热量OY的合作中进行。 PTS分析的主要结果是本文提出的。

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