Analysis of SDDR calculation method in a large tokamak model

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-29 DOI:10.1016/j.fusengdes.2025.115459

Ylenia Kogovšek Žiber , Klemen Ambrožič , Igor Lengar

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引用次数: 0

Abstract

Understanding the shutdown dose rate (SDDR) plays a crucial role in the operation and maintenance of a fusion reactor. It is particularly important to ensure the safety of personnel and the environment during maintenance and decommissioning phases. In addition, both the prediction and management of SDDR are necessary precautions in the design and operation of fusion reactors.

In the present study, SDDR is investigated on a simplified model of a large tokamak to achieve a better understanding of the calculation method, the rigorous two-step method (R2S). The JSIR2S code system, based on the R2S method, is currently being developed at the Jožef Stefan Institute and combines calculations with the MCNP transport code and the FISPACT inventory code. It has been evaluated against measurements at the TRIGA fission research reactor for fission applications, and in this work it is assessed for fusion applications as well.

The aim of this study is to perform SDDR calculations at different cooling times in a model of a fusion reactor using the JSIR2S code. An isotopic analysis was also carried out to identify the parent isotopes that contribute the most to the SDDR near the horizontal ports.

查看原文本刊更多论文

大型托卡马克模型SDDR计算方法分析

了解停堆剂量率（SDDR）在核聚变反应堆的运行和维护中起着至关重要的作用。在维护和退役阶段，确保人员和环境的安全尤为重要。此外，对SDDR的预测和管理是聚变反应堆设计和运行中必要的预防措施。在本研究中，为了更好地理解计算方法——严格两步法（R2S），我们在一个简化的大型托卡马克模型上研究了SDDR。基于R2S方法的JSIR2S代码系统目前正在Jožef Stefan研究所开发，并将计算与MCNP传输代码和FISPACT库存代码相结合。它已经在TRIGA裂变研究反应堆的裂变应用中进行了测量评估，在这项工作中，它也被评估为聚变应用。本研究的目的是使用JSIR2S代码在一个聚变反应堆模型中执行不同冷却时间下的SDDR计算。此外，还进行了同位素分析，以确定对水平端口附近SDDR贡献最大的母同位素。

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.