HZP and HFP rod ejection analysis in a SMART-like reactor model using the GUARDYAN-SUBCHANFLOW coupled code system

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

Annals of Nuclear Energy Pub Date : 2024-10-25 DOI:10.1016/j.anucene.2024.110988

Előd Pázmán , Gábor Tolnai , Dávid Légrády , Luigi Mercatali , Gianfranco Huaccho , Victor Hugo Sanchez-Espinoza

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引用次数: 0

Abstract

GUARDYAN is a dynamic 3D Monte Carlo reactor physics code with continuous energy handling developed for GPU hardware that has recently been coupled to the SUBCHANFLOW (SCF) subchannel thermal hydraulics solver. In this paper two control rod ejection accident scenarios will be presented in a Small Modular Reactor (SMR) geometry: a transient starting from Hot Zero Power (HZP), and one starting from Hot Full Power (HFP) conditions, both of them using Beginning of Cycle (BOC) material composition. Both the time dependent core-wise data and the node-wise data at certain times calculated by the GUARDYAN-SCF coupled code system exhibit the tendencies expected during such transients, with the thermal hydraulic properties mostly inside their safe limits. Relative variances estimated from 8 independent realisations suggest the results are credible. To further support our findings the HZP results are presented alongside data from PARCS-SCF and Serpent2-SCF calculations provided by Karlsruhe Institute of Technology (KIT), while for the HFP case we were able to compare some of the quantities to PARCS-SCF results.

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利用 GUARDYAN-SUBCHANFLOW 耦合代码系统对 SMART 类反应堆模型中的 HZP 和 HFP 棒喷射进行分析

GUARDYAN 是为 GPU 硬件开发的具有连续能量处理功能的动态三维蒙特卡洛反应堆物理代码，最近与 SUBCHANFLOW (SCF) 子通道热水力学求解器进行了耦合。本文将介绍小型模块化反应堆（SMR）几何结构中的两种控制棒弹射事故情景：一种是从热零功率（HZP）开始的瞬态情景，另一种是从热全功率（HFP）条件开始的瞬态情景，这两种情景都使用了循环开始（BOC）材料成分。由 GUARDYAN-SCF 耦合代码系统计算的随时间变化的堆芯数据和特定时间的节点数据都显示出在此类瞬态过程中的预期趋势，热液压特性大多在其安全范围内。通过 8 次独立实测估算出的相对方差表明结果是可信的。为了进一步支持我们的研究结果，我们将 HZP 结果与 PARCS-SCF 和 Serpent2-SCF 计算数据一起展示，后者由卡尔斯鲁厄理工学院（KIT）提供。

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.