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Views on R&D needs about in-vessel reflooding issues, with a focus on debris coolability

机译:对R&D需求的看法,涉及船内回注问题,着重于碎片的可冷却性

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In-vessel reflooding during a severe accident in a PWR was analyzed in 2000-2002 by a group of experts with the aim to prepare a global IRSN R&D strategy to answer the corresponding pending safety issues. Indeed, water is today systematically injected if available during a severe accident in a PWR. However, knowledge on consequences of such an injection is not complete and answers are necessary for accident management in present PWR as well for design and safety analysis of future PWR: is in-vessel corium retention possible? What is the kinetics of hydrogen production? What is the reactor cooling system (RCS) re-pressurization? Is there a risk of steam explosion (steam explosion is not discussed in this paper)? What is the impact on source term? And more generally, how to optimize water injection? (When? How?) R&D needs of investigation of these aspects were identified. This should cover separate-effect and integral tests, as well as modeling and code development. The approach consisted first in updating the synthesis of knowledge, based on the multiple reports released in an international frame (OECD, European Commission (EC) Framework Programs (FwP), ...), and then in focusing on a detailed re-analysis of the most important experiments CORA, QUENCH, LOFT-LP-FP2 and of TMI-2 accident, the latter two being directly related to debris coolability phenomena. Several out-of-pile experiments on debris bed coolability were also analyzed. A qualitative analysis of different possible core degradation scenarios was performed for French PWR, depending on operator actions or procedures. Simplified and mechanistic models were used to evaluate orders of magnitude of the phenomena in reactor conditions. A Phenomena Identification Ranking Table (PIRT) ranked the elementary phenomena with respect, on one hand, to their importance from the point of view of safety consequences and, on the other hand, to their level of understanding (often based on experts opinion). In particular, coolability of debris either in the core or in the lower plenum was identified as an important issue to be solved: uncertainties were underlined on debris characterization (size, distribution, composition,...) and on multi-D thermal-hydraulics in a debris bed. This ranking is fully consistent with the outcomes of the EURSAFE 5th FwP project. Existing or future experiments that could satisfy the needs were then identified, including for debris coolability POMECO, DEBRIS, STYX, etc. This specific issue will be analyzed in the frame of the Network of Excellence on severe accidents SARNET which has started in 2004 in the 6th FwP. Further model developments are being performed in the IRSN codes ICARE/CATHARE (detailed modeling) and ASTEC (simplified fast-running modeling), the latter being jointly developed with GRS.
机译:一组专家在2000-2002年对压水堆严重事故期间的船内回注进行了分析,目的是准备一项全球IRSN研发策略,以解决相应的未决安全问题。确实,如果在压水堆发生严重事故时可用,那么今天就会有系统地注入水。但是,有关这种注射后果的知识尚不完善,对于当前的PWR中的事故管理以及未来PWR的设计和安全性分析,都必须提供答案:是否可以在血管内保留钙?制氢的动力学是什么?什么是反应堆冷却系统(RCS)再加压?有蒸汽爆炸的危险(本文不讨论蒸汽爆炸)吗?对源术语有什么影响?更一般地说,如何优化注水? (何时?如何?)确定了研究这些方面的研发需求。这应该涵盖单独的效果测试和整体测试,以及建模和代码开发。该方法首先包括根据国际框架(经合组织,欧洲委员会(EC)框架计划(FwP)等)发布的多个报告来更新知识的综合,然后着重于详细的重新分析在CORA,QUENCH,LOFT-LP-FP2和TMI-2事故中最重要的实验中,后两个与碎片冷却性现象直接相关。还分析了关于碎屑床冷却性的几个桩外实验。对法国压水堆进行了不同可能的岩心退化方案的定性分析,具体取决于操作员的措施或程序。使用简化的机械模型来评估反应堆条件下现象的数量级。现象识别等级表(PIRT)一方面从安全后果的角度考虑基本现象的重要性,另一方面则从其理解水平(通常基于专家的观点)对基本现象进行了排序。尤其是,堆芯或下部增压室中的碎屑的可冷却性被确定为要解决的重要问题:在碎屑特征(尺寸,分布,组成等)和多维热工液压件上强调了不确定性在杂物床上该排名与EURSAFE第五个FwP项目的结果完全一致。然后确定了可以满足需求的现有或未来实验,包括碎片冷却能力POMECO,DEBRIS,STYX等。这一特定问题将在2004年开始于SARNET上的严重事故SARNET卓越网络框架中进行分析。第六轮正在用IRSN代码ICARE / CATHARE(详细建模)和ASTEC(简化的快速运行建模)进行进一步的模型开发,后者与GRS共同开发。

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