Abstract Treatment of plutonium separated from spent fuel has been one of the most important issues in the utilization of nuclear power in Japan. This study investigates a molten salt accelerator-driven system (ADS) to transmute transuranic (TRU) nuclides to address the issue. This study proposes the MARDS (Molten salt AcceleratoR Driven System) concept which has four features: employment of chloride, no dedicated spallation target, non-contact between beam window and fuel salt and modularized core. Neutronics calculation for the MARDS concept was performed for a condition of 400 MW thermal power with 800 MeV proton beam. The calculation results showed that the maximum proton beam current was about 7 mA and about 100–120 kg plutonium could be transmuted during one-year operation. The result indicates that the MARDS concept can employ a circular accelerator instead of LINAC and transmute TRU effectively.

中文翻译：

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TRU燃烧器熔盐加速器驱动系统的中子学设计

摘要 从乏燃料中分离出的钚的处理一直是日本核电利用中最重要的问题之一。本研究调查了熔盐加速器驱动系统 (ADS) 以嬗变超铀 (TRU) 核素以解决该问题。本研究提出了 MARDS（熔盐加速器驱动系统）概念，它具有四个特点：使用氯化物、没有专门的散裂目标、光束窗口与燃料盐之间的非接触以及模块化的堆芯。MARDS 概念的中子学计算是在 400 MW 热功率和 800 MeV 质子束的条件下进行的。计算结果表明，最大质子束电流约为 7 mA，运行 1 年可嬗变约 1​​00-120 kg 钚。