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THERMAL HYDRAULIC ANALYSIS OF PRESSURIZED THERMAL SHOCK FOR LOVIISA NPP USING APROS SIMULATION CODE

机译:使用APROS仿真代码,Loviisa NPP的加压热冲击热水力分析

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Loviisa Nuclear Power Plant consists of two VVER-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 led 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. Current operating licenses for Loviisa 1 and 2 Units reactor pressure vessels were applied by Fortum in 2012 to cover operation up to the years 2027 and 2030, respectively. The operating licenses were granted as applied by the Finnish Radiation and Nuclear Safety Authority (STUK) according to application. However a know-how of PTS scenarios shall be maintained. This becomes even more important in a light of any big power plant automation modernization projects targeting also safety systems. Currently Fortum is involved in an automation renewal project also known under its ELSA-project name. The project is scheduled to be ready in 2018. The project targets at replacing parts of old analogue automation with new digital systems and also extending their diversity by introducing new safety functions for emergency management scenarios. As a result, changes to some emergency operating procedures are inevitable. Due to the changes to emergency operating procedures PTS-scenarios for Loviisa NPP have been also updated. In 2016 Fortum launched PTS-project in connection with ELSA-project. Previous PTS-scenario related thermal hydraulic analyses were based on the original 80's decade analyses, which were subsequently revised many times following other modernization projects that took place at Loviisa NPP. In this new round of PTS-analyses the most important cases were recalculated using Apros (Advanced Process Simulator). ELSA-project introduced changes are not only emergency procedures specific but also involve safety system related process and automation logic modifications. The changes affected therefore boundary conditions needed in the analyses. In total probabilistic safety analyses included 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VVER-440型加压水反应堆单元组成,它由Finnish Energy Company 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。这导致了对加压热冲击(PTS)情景的广泛研究,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,对较低的过冷瞬态概率和减轻后果。 2012年Fortum应用了Loviisa 1和2个单元电抗器压力容器的当前运行许可证,分别涵盖了2027和2030年的操作。根据申请,芬兰辐射和核安全管理局(Stuk)授予运营许可证。然而,应保持PTS情景的诀窍。这在任何大型电厂自动化现代化项目瞄准安全系统的情况下,这变得更加重要。目前Fortum涉及在ELSA项目名称下也知道的自动化更新项目。该项目计划于2018年准备好。通过新的数字系统替换旧模拟自动化部分的项目目标,并通过引入紧急管理方案的新安全功能来扩展其多样性。因此,对某些紧急操作程序的变化是不可避免的。由于对Loviisa NPP的紧急操作程序的更改也已更新。 2016年Fortum推出了与Elsa-Project有关的PTS项目。以前的PTS场景相关的热液压分析基于原始的80年代的分析,随后在Loviisa NPP发生的其他现代化项目之后修改了多次。在这一新一轮PTS分析中,使用APROS(高级过程模拟器)重新计算最重要的情况。 ELSA-PROJECT引入的更改不仅是特定于应急程序,而且还涉及安全系统相关过程和自动化逻辑修改。因此,影响的变化受分析所需的边界条件。总概率安全分析包括超过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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