Coupled analysis system development on heat pipe reactor

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-06-01 Epub Date: 2025-03-27 DOI:10.1016/j.nucengdes.2025.114003

Sung Nam Lee, Sung Hoon Choi, Nam-il Tak, Hong-sik Lim, Chan Soo Kim

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Abstract

This study outlines the design tool and coupled analysis for heat transport in a space heat pipe reactor to provide power in a space environment for 10 years without fuel replacement. Korea Atomic Energy Research Institute (KAERI) has developed the design analysis tools to investigate the temperature distribution and maximum temperature in the reactor core. The neutronics code, McCARD, provides the power profile of the fuel compact in the core. The heat transport code, HEPITOS, predicts the temperature profiles coupled with the heat pipe analysis code, LUHPIS.

Since each code has different physics, the numerical calculation can be performed by the explicit method or the coupled method. Most studies have been analyzed using the coupled calculations of HEPITOS and LUHPIS. The coupled analysis with the neutronic code has been done to find out the feasibility of the coupled system development. The calculated results will be a reference for the evaluation of the thermal margins of the components.

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热管反应器耦合分析系统的开发

本研究概述了空间热管反应堆的热传输设计工具和耦合分析，以在不更换燃料的情况下在空间环境中提供10年的动力。韩国原子能研究所（KAERI）开发了设计分析工具，用于调查反应堆堆芯的温度分布和最高温度。中子代码，McCARD，提供了核心燃料紧凑体的功率分布。热传输代码HEPITOS与热管分析代码LUHPIS一起预测温度分布。由于每个代码具有不同的物理特性，因此可以采用显式方法或耦合方法进行数值计算。大多数研究都是使用HEPITOS和LUHPIS的耦合计算来分析的。通过与中子码的耦合分析，验证了耦合系统开发的可行性。计算结果将为构件热裕度的评定提供参考。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.