Evaluation of tritium production capability of the 5 MWe gas-cooled graphite-moderated reactor at Yongbyon using tritium-producing burnable absorber rods

IF 2.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Technology Pub Date : 2025-02-01 Epub Date: 2024-09-12 DOI:10.1016/j.net.2024.09.010
Dokyun Kim, Seong Jeong Jeong, Hyung Jin Shim
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Abstract

The 5 MWe graphite-moderated gas-cooled reactor located at Yongbyon, North Korea, is a major facility for producing nuclear materials. The objective of this study is to evaluate the tritium production capability of the 5 MWe reactor when using a tritium-producing burnable absorber rod (TPBAR). This paper presents burnup analysis results for TPBAR-embedded core models performed by McCARD, a Monte Carlo neutron transport simulation code. For three types of cores with TPBARs, the numerical results show that the 5 MWe reactor can produce 1.83–7.51 g of tritium per year depending on the number of TPBARs in the core. The numerical results can serve as a basis for assessing the feasibility of producing tritium using graphite-moderated gas-cooled reactors.
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评估宁边5mwe气冷石墨慢化反应堆使用产氚可燃吸收棒的产氚能力
位于北韩宁边的5mwe石墨慢化气冷反应堆是生产核材料的主要设施。本研究的目的是评估5 MWe反应堆在使用产氚可燃吸收棒(TPBAR)时的产氚能力。本文介绍了用蒙特卡罗中子输运模拟程序McCARD对嵌入tpbar的核模型进行燃耗分析的结果。对于三种类型的tpbar堆芯,数值结果表明,根据堆芯中tpbar的数量,5 MWe反应堆每年可产生1.83-7.51 g的氚。数值结果可作为评价石墨慢化气冷堆生产氚可行性的依据。
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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