Source term distribution and mobility – WP3 results of EU project SAMOSAFER

IF 2.5 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Nuclear Engineering and Design Pub Date : 2026-03-01 Epub Date: 2025-12-22 DOI:10.1016/j.nucengdes.2025.114679
J. Křepel , S. Lorenzi , L. Giot , E.M.A. Frederix , A. Cammi , F. Caruggi , S. Deanesi , F. Scioscioli , S. Delpech , P. Souček , J. Uhlíř , M. Mareček , M. Cihlář , J. Serp , H. Pitois , E. Merle , D. Rodrigues , C. Cannes , J. Kalilainen , S. Nichenko , T. Lind
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引用次数: 0

Abstract

The aim of the EU Horizon 2020 founded project SAMOSAFER was to develop and demonstrate new safety barriers and a more controlled behavior in severe accidents of the Molten Salt Reactor (MSR). The aim of work package 3 was to develop and validate models for tracing the nuclides carrying the radiotoxicity and decay heat, i.e. the source term and their chemical form and mobility during nominal and accidental conditions. The source term distribution at the beginning of an accident depends on the foregoing nominal operation mode. Hence, the liquid salt reprocessing and gaseous and insoluble Fission Products (FPs) separation was modeled before the severe accident simulation were accomplished. Because the source term assessment is a complex topic, only selected phenomena were addressed. As a reference system the MSFR concept was adopted from the previous EU project SAMOFAR. The study included benchmarking of the burnup tools, thermal-hydraulics simulations to confirm the removal rates to the off-gas system. Chemical experiments and calculations of the methods used in the reprocessing unit, simulation of severe accident conditions and finally calculation of the source term distribution. The major outcomes are the benchmark for the nuclide inventory tracing tools, application of multi-physics tools on He-bubbling for gaseous and solid FPs removal rates simulations, refinement of the reprocessing scheme, and first simulation of simplified severe accident.
源项分布和流动性——欧盟SAMOSAFER项目WP3结果
欧盟地平线2020成立的SAMOSAFER项目的目的是开发和展示新的安全屏障,并在熔盐堆(MSR)的严重事故中更好地控制行为。工作包3的目的是开发和验证模型,以追踪携带放射性毒性和衰变热的核素,即源项及其在名义和意外条件下的化学形式和迁移率。事故开始时的源项分布取决于上述标称运行模式。因此,在完成严重事故模拟之前,对液态盐后处理和气态和不溶性裂变产物(FPs)分离进行了建模。由于源项评估是一个复杂的主题,因此只讨论了选定的现象。作为一个参考系统,MSFR概念是从以前的欧盟SAMOFAR项目中采用的。该研究包括燃耗工具的基准测试,热工模拟,以确认废气系统的去除率。化学实验和计算方法应用于后处理单元,模拟严重事故条件,最后计算源项分布。主要成果包括核素库存追踪工具的基准,he -泡泡多物理场工具在气体和固体FPs去除速率模拟中的应用,后处理方案的改进以及简化严重事故的首次模拟。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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