Californium-252 production at the High Flux Isotope Reactor − I: Validation study using campaign data

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Donny Hartanto, David Chandler, Hailey Green, Jin Whan Bae, Kevin M. Burg, Yves Robert, Carol Sizemore
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Abstract

This paper presents a series of 252Cf production validation and code-to-code comparison studies performed based on data from the production campaigns at the High Flux Isotope Reactor (HFIR). These studies support efforts to convert HFIR from using highly enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. HFIR must maintain its world-class performance and missions following this conversion, and because 252Cf is a vital neutron-emitting radioisotope used for a variety of high-impact applications (e.g., reactor startup, cancer treatment), the ability to efficiently produce 252Cf must be preserved. In this work, the HFIRCON, Shift, ORIGEN, and TCOMP codes were deployed, and several sets of data libraries were investigated to better understand the calculation codes and the data biases. As-loaded target composition data, as-run irradiation history data, and post-irradiation measurements from recent multi-cycle irradiation campaigns of the HEU core were used to validate and determine methodology biases. The findings demonstrated a good agreement, with results falling within 3 standard deviations of measurements. This paper lays the ground work for the second paper, which evaluates and compares 252Cf production and safety metrics with the HEU core and a proposed LEU core.
高通量同位素反应堆的锎-252 生产--I:利用运行数据进行验证研究
本文基于高通量同位素反应堆(HFIR)生产活动的数据,介绍了一系列 252Cf 生产验证和代码间比较研究。这些研究为高通量同位素堆从使用高浓铀 (HEU) 燃料转换为低浓铀 (LEU) 燃料提供了支持。HFIR 必须在转换后保持其世界一流的性能和任务,由于 252Cf 是一种重要的中子发射放射性同位素,可用于各种高影响应用(如反应堆启动、癌症治疗),因此必须保持高效生产 252Cf 的能力。在这项工作中,部署了 HFIRCON、Shift、ORIGEN 和 TCOMP 代码,并对几组数据库进行了调查,以更好地了解计算代码和数据偏差。使用加载的目标成分数据、运行时的辐照历史数据以及高浓缩铀内核最近多周期辐照活动的辐照后测量数据来验证和确定方法偏差。研究结果表明,两者的一致性很好,结果与测量值的偏差在 3 个标准偏差以内。这篇论文为第二篇论文奠定了基础,第二篇论文将评估和比较高浓缩铀堆芯和拟议的低浓缩铀堆芯的 252Cf 生产和安全指标。
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
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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