Debris bed coolability in hypothetical core disruptive accidents: Theory, experiment, and numerical simulation review

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-03-09 DOI:10.1016/j.pnucene.2025.105700

Yonglong Li , Shaojie Tan , Yubin Lin , Kai Wang , Songbai Cheng

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引用次数: 0

Abstract

The coolability of debris beds in severe accidents of sodium-cooled fast reactors (SFRs) is critical for preventing radionuclide release, yet existing research has predominantly focused on light water reactors (LWRs), leaving a systematic analysis for SFRs lacking. This paper reviews debris bed coolability through theoretical models, experimental studies, and numerical simulations, while contrasting the distinctions between LWRs and SFRs. Theoretical models reveal that the inclusion or exclusion of interfacial drag marks a key divergence—models like Reed's, which neglect interfacial resistance, are suitable for high-flow bottom-flooding, whereas formulations such as Schulenberg-Müller's better align with top-flooding scenarios. Experimental findings demonstrate that particle size distribution, geometry, and porosity significantly influence dryout heat flux (DHF). Multidimensional cooling strategies (e.g., bottom-flooding or downcomers) disrupt countercurrent flooding limits (CCFL), enhancing DHF by 1.5–2.7 × compared to conventional top-flooding. Numerical simulations confirm the predictive capability of codes like MEWA and MELCOR for homogeneous debris beds, yet limitations persist in addressing SFR-specific challenges, such as high-temperature liquid metal coolant behavior and complex flow regimes. Future work must prioritize SFR-focused experiments, extend models to liquid metal conditions, and strengthen experimental-simulation synergies to improve risk assessment reliability. This paper provides theoretical and technical foundations for optimizing SFR severe accident management strategies.

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.