Study on the specifications of the basic core configurations of the modified STACY

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-01 DOI:10.1016/j.anucene.2024.110783
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Abstract

Since the compositions and properties of the fuel debris are uncertain, critical experiments are required to validate calculation codes and nuclear data used for the safety evaluation. For this purpose, the Japan Atomic Energy Agency (JAEA) has been modifying a critical assembly called “STACY.” The first criticality of the modified STACY is scheduled for spring 2024. This paper reports the consideration results of the core configurations of the modified STACY for the first criticality and inspections. The specifications of these core configurations were determined in advance, we tried to make them with a simplified computational model that considers the reactivity effect around the core. At the first criticality, two types of grid plates with different neutron moderation conditions (their hole spacings are 1.50  cm and 1.27  cm) were prepared. On the other hand, there is a limitation on the number of available UO2 fuel rods. The core configurations for the first criticality satisfying these experimental constraints were designed by computational analysis. A cylindrical core configuration with a 1.50  cm pitch grid plate close to the optimum moderation condition needs 253 fuel rods to reach criticality. As to the 1.27 cm grid plate, we considered core configurations with 2.54  cm intervals by using doubled pitches of the grid plate. It will need 213 fuel rods for the criticality to be reached. In addition, the experimental core configuration was considered with steel/concrete simulant rods to simulate fuel debris conditions. This paper shows six core configurations with different conditions, and all of them satisfy the regulatory requests.

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关于改进型 STACY 基本核心配置规格的研究
由于燃料碎片的成分和特性不确定,因此需要进行临界实验,以验证用于安全评估的计算代码和核数据。为此,日本原子能研究开发机构(JAEA)一直在修改一个名为 "STACY "的临界组件。改装后的 STACY 的首次临界时间定于 2024 年春季。本文报告了对改造后的 STACY 的堆芯配置进行首次临界和检查的审议结果。这些堆芯构型的规格是事先确定的,我们试图通过一个考虑到堆芯周围反应性效应的简化计算模型来制作它们。在第一次临界时,我们准备了两种具有不同中子慢化条件的网格板(孔间距分别为 1.50 厘米和 1.27 厘米)。另一方面,可用的氧化铀燃料棒数量有限。通过计算分析,设计出了满足这些实验限制条件的首次临界堆芯构型。间距为 1.50 厘米的圆柱形堆芯构型接近最佳节制条件,需要 253 根燃料棒才能达到临界。至于 1.27 厘米间距的栅板,我们考虑了间距为 2.54 厘米的堆芯构型,将栅板间距加倍。达到临界状态需要 213 根燃料棒。此外,我们还考虑了使用钢/混凝土模拟棒的实验堆芯配置,以模拟燃料碎片情况。本文展示了六种不同条件下的堆芯配置,所有这些配置都能满足规范要求。
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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