SCALE inventory and reactivity analysis as part of the Hermes 2021 PSAR review

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

Annals of Nuclear Energy Pub Date : 2024-11-25 DOI:10.1016/j.anucene.2024.111063

Friederike Bostelmann , Benjamin R. Betzler , Donny Hartanto , William A. Wieselquist

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引用次数: 0

Abstract

The readiness of SCALE for comprehensive studies of pebble-bed reactors has been demonstrated through detailed analysis of a fluoride salt–cooled, high-temperature pebble-bed reactor (PB-FHR). The methods developed for pebble-bed reactor modeling in SCALE, particularly for inventory generation, have proven effective in gaining insights into the reactor physics of this advanced reactor. Excellent agreement with another code package has been observed, further highlighting SCALE’s strong performance.

The SCALE results supported the US Nuclear Regulatory Commission’s construction permit application review of the Hermes low-power PB-FHR demonstration reactor. A SCALE model of the Hermes reactor was developed at Oak Ridge National Laboratory using information from the Preliminary Safety Analysis Report (PSAR) and supplemented with publicly available data. SCALE reactivity coefficient simulations reproduced PSAR results within 1

σ

statistical uncertainties. Sensitivity studies emphasized the importance of graphite specifications for accurate k_eff predictions.

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作为赫尔墨斯 2021 PSAR 审查一部分的 SCALE 清单和反应性分析

通过对氟化盐冷却高温鹅卵石床反应器（PB-FHR）的详细分析，证明了 SCALE 可用于鹅卵石床反应器的综合研究。事实证明，在 SCALE 中开发的鹅卵石床反应器建模方法，特别是生成清单的方法，可以有效地深入了解这种先进反应器的反应器物理特性。SCALE 的结果为美国核管理委员会审查赫尔墨斯低功率 PB-FHR 示范反应堆的施工许可申请提供了支持。橡树岭国家实验室利用初步安全分析报告（PSAR）中的信息，并辅以公开数据，开发出了赫尔墨斯反应堆的 SCALE 模型。SCALE 反应系数模拟再现了 PSAR 的结果，统计不确定性在 1σ 以内。敏感性研究强调了石墨规格对准确预测 keff 的重要性。

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

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.