Development and application of safety analysis code for He-Xe cooled space reactor

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-02-17 DOI:10.1016/j.nucengdes.2025.113914

Ming Liu , Pan Wu , Ke Huang , Jianqiang Shan

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引用次数: 0

Abstract

Space nuclear reactor power system can offer high energy density and a wide power coverage, providing electric power for space exploration. The safety characteristics of space nuclear reactor during in-orbit operation accidents is key to evaluate its feasibility. In this paper, a safety analysis code is developed for He-Xe mixture cooled space reactor based on SCTRAN, which used to be applied for Supercritical water or CO₂ cooled reactor. A semi empirical formula is applied to develop a physical property calculation model of He–Xe. Flow resistance and heat transfer correlations as well as turbomachinery models for He-Xe are developed. A numerical model for S⁴-CBC space reactor power system is established by using the newly developed code. The calculation results of reactor and system model have the maximum relative errors of 3.43 % and 0.47 % compared to the reference design values, which proves the code is reliable to simulate the thermal–hydraulic behavior of the S⁴-CBC space reactor power system. The transient responses of the S⁴-CBC space reactor power system under the reactivity insertion accident and the mechanical failure of one and two Brayton loops are simulated and analyzed. The results of the accident analysis provide guidance for the core design, operation strategy, and safety system design of future He-Xe cooled space reactor system.

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来源期刊

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.