Past and Future Research at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident-Reference-Cited by-同舟云学术

Past and Future Research at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Published:2016-11 Issue:2 Volume:196 Page:161-174
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Jacquemain Didier¹,Vola Didier¹,Meignen Renaud¹,Bonnet Jean-Michel¹,Fichot Florian¹,Raimond Emmanuel¹,Barrachin Marc¹

Affiliation:

1. Institut de Radioprotection et de Sùreté Nucléaire (IRSN), Nuclear Safety Division/Safety Research/Severe Accident Department, Saint Paul Lez Durance, 13115, France

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT16-13

Reference6 articles.

1. “OECD SERENA Project Report—Summary and Conclusion,” NEA/CSNI/R(2014)15, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2015).

2. J. M. SEILER et al. “Analysis of Corium Recovery Concepts by the EUROCORE Group,” SAM-EUROCORE Report 08 (2002).

3. M. EPSTEIN, “Review of Water Ingression Models,” ACEX-TR-CD31, Fauske Associates, EPRI (Mar. 2000).

4. M. T. FARMER et al. “OECD MCCI Project Final Report,” OECD/MCCI-2005-TR06, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (Feb. 2006).

5. R. J. LIPINSKI, “A Model for Boiling and Dry-Out in Particle Beds,” NUREG/CR-2646, SAND82-0765, Sandia National Laboratories (June 1982).

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Multi-scale simulation of microstructural evolution for molten U–Zr–O ternary system;Journal of Nuclear Materials;2024-08

2. Solidification and re-melting mechanisms of SUS-B4C eutectic mixture;Journal of Nuclear Materials;2021-01

3. Dissolution behavior of solid stainless steel by its molten eutectic mixture with B4C under dynamic condition;Progress in Nuclear Energy;2019-11

4. Investigation of corrosion-erosion behavior of stainless steel considering SS-B4C melt;Journal of Nuclear Materials;2019-03

5. Experimental justification of strainer meshes of NPP sump;MAG CIV ENG;2018