Abstract
European lead fast reactor designs are all pool-type designs. The pool basically forms the primary system of the reactor and as such plays a crucial role in the design and safety analyses of such reactors. The safety analyses require thorough understanding of the flow and heat transport in the primary system. In the past, the design and safety analysis of liquid metal cooled reactors highly relied on design specific experimental set-ups using either a transparent, easy-to-handle simulant fluid relying on scaling analyses or using liquid metals while coping with measurement limitations. Nowadays, Computational Fluid Dynamics (CFD) has become an integral tool of the advanced reactor designer allowing simulations in 3 dimensions. However, in a heavy liquid metal pool, many complex physical phenomena come together. As such, these simulations need separate validation of the capabilities of the applied CFD codes and, on top of that, integral validation using large scale experimental facilities. This paper discusses the ongoing efforts at NRG in the Netherlands on validation of CFD tools for heavy liquid metal pool simulations with respect to flow and heat transport.
| Original language | English |
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| Pages | 109-116 |
| Number of pages | 8 |
| State | Published - 2018 |
| Externally published | Yes |
| Event | International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting - Orlando, United States Duration: 11 Nov 2018 → 15 Nov 2018 |
Conference
| Conference | International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting |
|---|---|
| Country/Territory | United States |
| City | Orlando |
| Period | 11/11/18 → 15/11/18 |
Bibliographical note
Publisher Copyright:© 2018 International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting. All rights reserved.
Keywords
- CFD
- HLM
- Lead
- Lead-bismuth
- Reactor pool
ASJC Scopus subject areas
- Geotechnical Engineering and Engineering Geology
- Nuclear Energy and Engineering
- Nuclear and High Energy Physics