Utilization of thorium in accelerator driven subcritical system

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-07-08 DOI:10.1016/j.anucene.2025.111728

Shijie Du , Xiang Wu , Peng Fang , Qiuying Liang , Yongwei Yang , Feng Zhou , Yanling Zhu , Lei Yang

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引用次数: 0

Abstract

Accelerator Driven subcritical System (ADS) is characterized by high intrinsic safety. And the Thorium-based Molten Salt Reactor (TMSR) has the advantages of utilization of abundant fuel resources with good fuel breeding performance. Combining the characteristics of the above two systems, we study an accelerator-driven thorium-based molten salt reactor for the utilization of Thorium. The reactor burnup process was simulated using IMPC-Burnup2.0 code, and online refueling functionality was added. We design five models with different fuel pipe diameters. The final yields of ²³³U for the five models with pipe diameters of 3 cm, 4 cm, 5 cm, 6 cm and 7 cm are 209.90 kg, 407.85 kg, 671.27 kg, 977.33 kg and 1306.20 kg, respectively. And the reactor fuel doubling periods are 690 days, 1410 days and 2940 days at pipe diameters of 3 cm, 4 cm and 5 cm, respectively. This study verifies that the accelerator-driven molten-salt thorium reactors have good thorium-uranium breeding performance.

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钍在加速器驱动亚临界系统中的应用

加速器驱动的亚临界系统（ADS）具有较高的本质安全性。钍基熔盐堆（TMSR）具有燃料资源利用丰富、燃料增殖性能好等优点。结合上述两种体系的特点，我们研究了一种加速器驱动的钍基熔盐反应堆，用于钍的利用。使用IMPC-Burnup2.0代码模拟了反应堆燃用过程，并增加了在线加油功能。我们设计了五种不同燃料管直径的型号。管径为3cm、4cm、5cm、6cm和7cm的5种型号，233U的最终产率分别为209.90 kg、407.85 kg、671.27 kg、977.33 kg和1306.20 kg。在管径为3cm、4cm和5cm时，反应堆燃料倍增周期分别为690天、1410天和2940天。本研究验证了加速器驱动熔盐钍堆具有良好的钍铀增殖性能。

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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.