The decay heat distribution calculation in molten salt reactor experiment based on the nuclide flow-transfer-burnup coupling method

IF 3.2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-09-25 DOI:10.1016/j.pnucene.2025.106060

Zhenghao Xu , Guifeng Zhu , Liang Chen , Shuyang Jia , Changqing Yu , Yunfei Zhang , Yang Zou , Hongjie Xu

{"title":"The decay heat distribution calculation in molten salt reactor experiment based on the nuclide flow-transfer-burnup coupling method","authors":"Zhenghao Xu , Guifeng Zhu , Liang Chen , Shuyang Jia , Changqing Yu , Yunfei Zhang , Yang Zou , Hongjie Xu","doi":"10.1016/j.pnucene.2025.106060","DOIUrl":null,"url":null,"abstract":"<div><div>The liquid-fueled molten salt reactor (MSR), unique among Generation IV systems, presents novel challenges due to its circulating fuel's multi-phase decay heat distribution. This study develops a nuclide flow-transfer-burnup coupling method to analyze spatiotemporal decay heat characteristics in MSRs. By analyze 8 MW Molten Salt Reactor Experiment (MSRE) primary loop, we find that, Short-lived nuclides (1s-1min half-life) contribute ∼40 % of equilibrium decay heat but rapidly decay when leaving the core, leading to flow-dependent spatial non-uniformity; While most decay heat (∼70 %) remains in salt, long-lived insoluble nuclides accumulate at high-surface-area components (e.g., heat exchangers); After reactor shutdown, salt-phase decay heat drops rapidly while wall-deposited nuclides maintain long-term heat output. Our framework enables accurate decay heat analysis under all operational conditions, revealing significant spatial heterogeneity both within and beyond the fuel salt (wall phase, gas phase, gas-remove systems). These findings are crucial for decay heat removal system design. Current uncertainties in bubble dynamics and mass transfer coefficients require further experimental validation.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106060"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025004585","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

The liquid-fueled molten salt reactor (MSR), unique among Generation IV systems, presents novel challenges due to its circulating fuel's multi-phase decay heat distribution. This study develops a nuclide flow-transfer-burnup coupling method to analyze spatiotemporal decay heat characteristics in MSRs. By analyze 8 MW Molten Salt Reactor Experiment (MSRE) primary loop, we find that, Short-lived nuclides (1s-1min half-life) contribute ∼40 % of equilibrium decay heat but rapidly decay when leaving the core, leading to flow-dependent spatial non-uniformity; While most decay heat (∼70 %) remains in salt, long-lived insoluble nuclides accumulate at high-surface-area components (e.g., heat exchangers); After reactor shutdown, salt-phase decay heat drops rapidly while wall-deposited nuclides maintain long-term heat output. Our framework enables accurate decay heat analysis under all operational conditions, revealing significant spatial heterogeneity both within and beyond the fuel salt (wall phase, gas phase, gas-remove systems). These findings are crucial for decay heat removal system design. Current uncertainties in bubble dynamics and mass transfer coefficients require further experimental validation.

查看原文本刊更多论文

基于核素流动-传递-燃耗耦合法的熔盐堆实验衰变热分布计算

液体燃料熔盐堆（MSR）在第四代系统中是独一无二的，由于其循环燃料的多相衰变热分布，提出了新的挑战。本研究提出一种核素流动-传递-燃耗耦合方法来分析MSRs的时空衰减热特性。通过对8mw熔盐堆实验（MSRE）一次回路的分析发现，短寿命核素（1s-1min半衰期）贡献了~ 40%的平衡衰减热，但在离开堆芯后迅速衰减，导致流动相关的空间非均匀性；虽然大多数衰变热（约70%）留在盐中，但长寿命的不溶性核素积聚在高表面积组件（例如热交换器）中；反应堆关闭后，盐相衰变热迅速下降，而壁上沉积的核素保持长期的热输出。我们的框架能够在所有运行条件下进行精确的衰变热分析，揭示燃料盐内外（壁相、气相、除气系统）的显著空间异质性。这些发现对于设计衰变排热系统至关重要。目前气泡动力学和传质系数的不确定性需要进一步的实验验证。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

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.