Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-09-26 DOI:10.1016/j.anucene.2024.110917
Yaqi Wang , Zachary M. Prince , Hansol Park , Olin W. Calvin , Namjae Choi , Yeon Sang Jung , Sebastian Schunert , Shikhar Kumar , Joshua T. Hanophy , Vincent M. Labouré , Changho Lee , Javier Ortensi , Logan H. Harbour , Jackson R. Harter
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Abstract

Griffin is a Multiphysics Object-Oriented Simulation Environment (MOOSE) based reactor physics application for multiphysics simulations of advanced reactor designs jointly developed by Idaho National Laboratory and Argonne National Laboratory. This paper summarizes the motivation, significance, architecture, design, and features of Griffin. Griffin offers flexible and extensible features to address the challenges associated with advanced reactor designs. These features range from fundamental particle transport to specific reactor physics tasks. The features cover a wide range including on-the-fly and traditional two-step cross-section generation methods, steady-state and transient transport solvers suitable for both heterogeneous and homogeneous models, high-fidelity depletion where thousands of isotopes can be tracked and low-fidelity depletion characterized by burnup, etc. The most fundamental aspect that sets Griffin apart from other reactor analysis codes is that it is developed based on the MOOSE framework. A modular development approach is strongly enforced, with multiphysics being an essential element considered since the beginning of Griffin’s development. Griffin links various MOOSE physics modules and couples to other MOOSE-based applications and non-MOOSE-based applications for multiphyiscs simulations. Griffin includes three modules: ISOXML for preparing and managing multigroup cross sections, radiation transport for solving the neutron transport equation, and reactor analysis for user-oriented reactor physics analysis functionalities. Griffin uses various finite element methods for spatial discretization, multigroup approximation for energy discretization and discrete ordinates method, spherical harmonics expansion method, and diffusion approximation for streaming direction discretization to solve the neutron transport equation. Griffin’s flexibility is evidenced through Griffin’s various applications to fast reactor, high-temperature reactor, pebble bed reactor, molten salt reactor, and microreactor designs. Griffin development follows the software quality assurance procedure for MOOSE-based applications and with software requirements consistent with the ASME NQA-1 standard. Griffin has been adopted into the reactor analysis system for the U.S. NRC and is in use at U.S. companies, universities and national laboratories.
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格里芬基于 MOOSE 的反应堆物理应用程序,用于先进核反应堆的多物理场模拟
Griffin 是爱达荷国家实验室和阿贡国家实验室联合开发的基于多物理场面向对象仿真环境 (MOOSE) 的反应堆物理应用程序,用于先进反应堆设计的多物理场仿真。本文概述了 Griffin 的开发动机、意义、架构、设计和功能。Griffin 提供了灵活和可扩展的功能,以应对与先进反应堆设计相关的挑战。这些功能包括从基本粒子传输到特定反应堆物理任务的各种功能。这些功能涵盖的范围很广,包括即时和传统的两步截面生成方法、适用于异质和均质模型的稳态和瞬态输运求解器、可跟踪数千种同位素的高保真损耗和以燃烧为特征的低保真损耗等。Griffin 有别于其他反应堆分析代码的最根本之处在于它是基于 MOOSE 框架开发的。它采用模块化开发方法,多物理场是 Griffin 开发之初就考虑的基本要素。Griffin 将各种 MOOSE 物理模块连接起来,并与其他基于 MOOSE 的应用程序和非基于 MOOSE 的应用程序耦合,用于多物理场模拟。Griffin 包括三个模块ISOXML 用于准备和管理多组截面,辐射传输用于求解中子传输方程,反应堆分析用于面向用户的反应堆物理分析功能。Griffin 使用各种有限元方法进行空间离散化,使用多组近似法进行能量离散化和离散序数法、球谐波展开法和扩散近似法进行流向离散化,以求解中子输运方程。Griffin 在快堆、高温堆、鹅卵石床堆、熔盐堆和微堆设计中的各种应用证明了其灵活性。Griffin 的开发遵循基于 MOOSE 的应用软件质量保证程序,软件要求符合 ASME NQA-1 标准。Griffin 已被美国国家反应堆委员会采用为反应堆分析系统,并在美国公司、大学和国家实验室使用。
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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