S. T. R. Andika Putra Dwijayanto, I. Husnayani, Z. Zuhair
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引用次数: 5
摘要
钍循环实验动力堆乏燃料中放射性核素的特性。在htgr为基础的实验动力反应堆(Reaktor Daya ekexperimental /RDE)中有几种核燃料利用的选择。虽然RDE主要使用低浓缩铀(LEU)燃料,这是目前最可行的选择,但RDE也可能使用其他燃料,例如钍基燃料,甚至可能是钚基燃料。不同的燃料产生不同的乏燃料特性,因此有必要对其特性进行识别,以了解和评价其处理和临时储存。本文在典型运行循环条件下,对含钍RDE乏燃料的特性进行了研究。使用ORIGEN2.1代码确定乏燃料特性。结果表明,在计算周期结束时,每个钍基乏燃料球产生约0,627瓦的热量,28个中子/秒,8.28 × 1012个光子/秒,并产生192.53居里的放射性。如果RDE使用钍基燃料,这些较高的放射性和光子发射可能需要在乏燃料管理方面采取不同的措施。Tl-208的活动被发现可能发出不可忽略的强伽马辐射,这增加了对适当处理乏燃料的要求,特别是在乏燃料桶中进行辐射屏蔽。关键词:RDE,乏燃料,钍,HTGR, Tl-208
CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL.
CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL. There are several options of nuclear fuel utilisation in the HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE). Although mainly RDE utilises low enriched uranium (LEU)-based fuel, which is the most viable option at the moment, it is possible for RDE to utilise other fuel, for example thorium-based and possibly even plutonium-based fuel. Different fuel yields different spent fuel characteristics, so it is necessary to identify the characteristics to understand and evaluate their handling and interim storage. This paper provides the study on the characteristics of thorium-fuelled RDE spent fuel, assuming typical operational cycle. ORIGEN2.1 code is employed to determine the spent fuel characteristics. The result showed that at the end of the calculation cycle, each thorium-based spent fuel pebble generates around 0,627 Watts of heat, 28 neutrons/s, 8.28x1012 photons/s and yield 192.53 curies of radioactivity. These higher radioactivity and photon emission possibly necessitate different measures in spent fuel management, if RDE were to use thorium-based fuel. Tl-208 activity, which found to be emitting potentially non-negligible strong gamma emission, magnified the requirement of proper spent fuel handling especially radiation shielding in spent fuel cask.Keywords: RDE, spent fuel, thorium, HTGR, Tl-208.