TRACE assessment of density wave instability onset with void reactivity feedback under natural circulation

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology Pub Date : 2024-09-01 DOI:10.1016/j.net.2024.08.064

Paul Hurley, Yang Liu, Tomasz Kozlowski, Juliana P. Duarte

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引用次数: 0

Abstract

Density wave oscillation (DWO) is an important safety concern for boiling water reactors (BWR) due to their high void fraction in the core. Power extensions to existing reactors such as the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) lead to increase susceptibility of DWO-type instability following an anticipated transient without scram (ATWS). Experiments performed at the Karlstein Thermal Hydraulic Test Facility (KATHY) have reproduced the reactivity feedback mechanism in BWRs under ATWS conditions. Using a neutronics module simulator, the KATHY facility was able to provide data on the effect of different neutronic parameters on DWO onset. This paper serves to assess the capability of the thermal-hydraulics code TRACE V5P7 for simulating DWO onset and development under natural circulation with neutronic feedback. A model of the KATHY natural circulation facility is created in TRACE and a reactivity feedback mechanism is implemented using a manual control scheme to simulate the parametric effects provided by the tests. This comparison allows for an assessment of the TRACE code as well as a better understanding of the instability mechanisms and behavior under the given conditions.

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利用自然环流下的空隙反应反馈对密度波不稳定性的 TRACE 评估

密度波振荡（DWO）是沸水反应堆（BWR）的一个重要安全问题，因为其堆芯中的空隙率很高。现有反应堆的功率扩展，如最大扩展负荷线极限分析增强版（MELLLA+），导致在预期无扰动瞬态（ATWS）之后更容易出现 DWO 型不稳定性。在卡尔斯坦热工水力试验设施（KATHY）进行的实验再现了在 ATWS 条件下生物质反应堆的反应反馈机制。利用中子模块模拟器，KATHY 设备能够提供不同中子参数对 DWO 发生影响的数据。本文旨在评估 TRACE V5P7 热工水力代码在自然循环和中子反馈条件下模拟 DWO 发生和发展的能力。在 TRACE 中创建了 KATHY 自然循环设施模型，并使用手动控制方案实施了反应反馈机制，以模拟试验提供的参数效应。通过比较，可以对 TRACE 代码进行评估，并更好地了解给定条件下的不稳定机制和行为。

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