Benchmark analysis of SPERT III E-core critical experiments using the STREAM neutronics code

IF 2.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2025-12-31 DOI:10.1016/j.net.2025.104112

Anisur Rahman , Saisundar Mohanty , Deokjung Lee

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引用次数: 0

Abstract

This study delivers a high-fidelity neutronic analysis of the SPERT III E-Core, a pressurized-water experimental reactor designed to probe fundamental transient behavior during reactivity-initiated accidents (RIAs). Using the advanced 3D transport code STREAM, we construct a detailed full-core representation—including fuel assemblies, cruciform transient control rods, control rod followers, and flux suppressors, to simulate both steady-state operation and rapid power excursions. Eigenvalue predictions at cold and hot zero-power conditions agree with measurements within 400 pcm, while simulated RIA responses, including reactivity evolution, peak power, and energy release, remain within 10 % of experimental observations. These results demonstrate that STREAM reliably captures fast transient dynamics in complex reactor configurations. Beyond validating a modern deterministic tool against historically important pulse-reactor experiments, this work establishes a foundation for next-generation transient modeling, supporting enhanced safety assessment, performance optimization, and informed regulatory decision-making in advanced reactor systems.

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使用STREAM中子码对SPERT III E-core临界实验进行基准分析

这项研究提供了SPERT III E-Core的高保真中子分析，这是一种压水实验反应堆，旨在探测反应性引发事故（ria）期间的基本瞬态行为。使用先进的3D传输代码STREAM，我们构建了一个详细的全核心表示-包括燃料组件，十字形瞬态控制棒，控制棒跟随器和通量抑制器，以模拟稳态运行和快速功率漂移。冷、热零功率条件下的特征值预测与400 pcm以内的测量结果一致，而模拟的RIA响应，包括反应性演化、峰值功率和能量释放，与实验观测值的误差仍在10%以内。这些结果表明STREAM可靠地捕获了复杂反应堆结构中的快速瞬态动力学。除了通过历史上重要的脉冲反应堆实验验证现代确定性工具之外，这项工作还为下一代瞬态建模奠定了基础，支持先进反应堆系统中增强的安全评估、性能优化和知情的监管决策。

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 Technology 工程技术-核科学技术

CiteScore

4.80

自引率

7.40%

发文量

431

审稿时长

3.5 months

期刊介绍： Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development