Generic material irradiation database for delayed heating calculations

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

Nuclear Engineering and Design Pub Date : 2024-10-24 DOI:10.1016/j.nucengdes.2024.113634

Roberto E. Fairhurst-Agosta, Tomasz Kozlowski

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引用次数: 0

Abstract

Safety analyses in research reactors require the estimation of heat deposited in experiments and reactor structures after shutdown. The accurate assessment of the deposited energy across a reactor geometry better determines the heat removal requirements and ensures effective cooling. However, the development of experiment safety analyses on a case-by-case basis often proves to be effort and time-consuming. This article introduces a method based on the creation of a generic material irradiation database to expedite the process. The irradiation database is created by calculating the delayed heating in experiments of individual chemical elements. Then, the created database enables the quick calculation of the delayed heating of experiments of arbitrary material composition. This article showcases two applications to demonstrate the delayed heating calculation workflow and verify the generic material irradiation database method. These applications include a simple demonstration exercise and an Advanced Test Reactor experiment. The results display an overall good agreement between the generic material irradiation database method and reference values for a wide variety of experiments.

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用于延迟加热计算的通用材料辐照数据库

研究反应堆的安全分析需要对停堆后沉积在实验和反应堆结构中的热量进行估算。对反应堆几何结构中沉积能量的准确评估可以更好地确定散热要求，并确保有效冷却。然而，根据具体情况进行实验安全分析往往费时费力。本文介绍了一种基于创建通用材料辐照数据库的方法，以加快这一过程。辐照数据库是通过计算单个化学元素实验中的延迟加热而创建的。然后，创建的数据库可以快速计算任意材料成分实验的延迟加热。本文展示了两个应用程序，以演示延迟加热计算工作流程并验证通用材料辐照数据库方法。这些应用包括一个简单的演示练习和一个高级试验反应堆实验。结果表明，通用材料辐照数据库方法与各种实验的参考值之间总体上具有良好的一致性。

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.