Dose assessment for radioactive products distributed on liquid Li loops of fusion neutron sources

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-05-01 Epub Date: 2025-02-27 DOI:10.1016/j.fusengdes.2025.114901
Shunsuke Kenjo, Makoto Oyaidzu, Saerom Kwon, Kentaro Ochiai, Satoshi Sato
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Abstract

Radiation dose rates around liquid Li loops in International Fusion Materials Irradiation Facility (IFMIF)-like fusion neutron sources, such as A-FNS, increase because of the radionuclides produced by high-energy deuterons and neutrons. This study assesses radiation dose rates around the pipe, heat exchanger (HX), and electromagnetic pump (EMP) of a liquid Li loop using the Monte Carlo code MCNP6.2 and the photon data library mcplib84 to advance the development of maintenance strategies. The radiation sources include not only major nuclides (tritium and Be-7) reported in previous studies but also other radionuclides that have not been well investigated thus far. The calculation results suggest that hands-on maintenance of Li pipes can be performed after the Li drain. However, accesses HX and EMP are limited because of nuclides such as Y-88, which are produced from impurities in liquid Li, even when Be-7 is trapped in Cold Trap.
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核聚变中子源液态Li环上放射性产物的剂量评估
在类似国际聚变材料辐照设施(IFMIF)的聚变中子源(如A-FNS)中,液态Li环周围的辐射剂量率由于高能氘核和中子产生的放射性核素而增加。本研究利用蒙特卡罗代码MCNP6.2和光子数据库mcplib84,对液态锂环路的管道、热交换器(HX)和电磁泵(EMP)周围的辐射剂量率进行了评估,以促进维护策略的发展。这些辐射源不仅包括以往研究中报道的主要核素(氚和Be-7),还包括迄今尚未得到充分研究的其他放射性核素。计算结果表明,可以在排锂后对管道进行手工维护。然而,即使Be-7被困在冷阱中,HX和EMP的获取也受到限制,因为Y-88等核素是由液态Li中的杂质产生的。
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来源期刊
Fusion Engineering and Design
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.
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