Novel modular and Git-based approach for the management and development of radiation transport models

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

Fusion Engineering and Design Pub Date : 2025-06-07 DOI:10.1016/j.fusengdes.2025.115248

A. Cubi, M. Fabbri, M. Cavinato, A. Jokinen, A. Ripollès, A. Portone

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引用次数: 0

Abstract

Radiation transport models are essential for the safe design of fission and fusion nuclear reactors. The increase of computational resources, advancement of developing tools and the level of detail required in neutronics assessments have resulted in a significant increase of the complexity of the models. The current methodologies for development and management of radiation transport models presents important challenges like large input files, collaboration barriers, version control issues and a lack of error tracking. This paper proposes Gitronics: a novel modular and Git-based approach for the management of radiation transport models. Gitronics includes an ad-hoc developed Python package that allows the division of a model into smaller independent files. This modularization synergizes with the use of the robust version control system Git. A transport model becomes therefore a Git repository that can be hosted in platforms like GitLab for enhanced collaboration and management. A pilot study of Gitronics is presented for the JT-60SA neutronics reactor model.

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新的模块化和基于git的方法来管理和发展辐射输运模型

辐射输运模型对于裂变和聚变核反应堆的安全设计至关重要。计算资源的增加、开发工具的进步以及中子评估所需的详细程度导致了模型复杂性的显著增加。目前用于开发和管理辐射传输模型的方法提出了一些重要的挑战，如大型输入文件、协作障碍、版本控制问题和缺乏错误跟踪。本文提出了Gitronics：一种新的模块化和基于git的辐射传输模型管理方法。Gitronics包含一个特别开发的Python包，它允许将模型划分为更小的独立文件。这种模块化与健壮的版本控制系统Git的使用协同作用。因此，传输模型变成了一个Git存储库，可以托管在像GitLab这样的平台上，以增强协作和管理。介绍了JT-60SA中子反应堆模型的电子学中试研究。

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

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.