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KANG, JUNGMIN (5) answer(s).
 
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1
ID:   077015


Feasibility of converting Russian icebreaker reactors from HEU / Diakov, Anatoli C; Dmitriev, Alexander M; Kang, Jungmin; Shuvayev, Alexey M   Journal Article
Kang, Jungmin Journal Article
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Publication 2007.
Summary/Abstract A considerable amount of experience has been accumulated in converting compact research reactors from highly-enriched uranium (HEU) to low-enriched uranium (LEU). Although the details of naval-reactor design are closely held military secrets, during the Gorbachev period, the Soviet Union supplied the Norwegian government with some basic data, including the dimensions and 235U content of the core of the HEU fueled KLT-40 reactor used in some Russian nuclear-powered icebreakers. A group of Norwegian analysts used this information to develop a simple model of the KLT-40 core. We have calculated the neutronics behaviors of variants of these core models as a function of 235U burnup and conclude that the reactors could be fueled with LEU without loss of core life. We also show that simplified infinite-core calculations can be used for such studies
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2
ID:   110360


Future regional nuclear fuel cycle cooperation in East Asia: energy security costs and benefits / Hippel, David von; Hayes, Peter; Kang, Jungmin; Katsuta, Tadahiro   Journal Article
Hayes, Peter Journal Article
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Publication 2011.
Summary/Abstract Economic growth in East Asia has rapidly increased regional energy, and especially, electricity needs. Many of the countries of East Asia have sought or are seeking to diversify their energy sources and bolster their energy supply and/or environmental security by developing nuclear power. Rapid development of nuclear power in East Asia brings with it concerns regarding nuclear weapons proliferation associated with uranium enrichment and spent nuclear fuel management. This article summarizes the development and analysis of four different scenarios of nuclear fuel cycle management in East Asia, including a scenario where each major nuclear power user develops uranium enrichment and reprocessing of spent fuel individually, scenarios featuring cooperation in the full fuel cycle, and a scenario where reprocessing is avoided in favor of dry cask storage of spent fuel. The material inputs and outputs and costs of key fuel cycle elements under each scenario are summarized.
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3
ID:   066986


Limited proliferation-resistance bebefitis from recycling unsep / Kang, Jungmin; Hippel, Frank Von 2005  Journal Article
Kang, Jungmin Journal Article
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Publication 2005.
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4
ID:   059109


South Korea's nuclear surprise / Kang, Jungmin; Hayes, Peter; Bin, Li Jan-Feb 2005  Journal Article
Hayes, Peter Journal Article
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Publication Jan-Feb 2005.
Key Words NPT  ;  South Korea-Nuclear  ;  IAEA  ;  South Korea  ;  Nuclear Non Proligferation 
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5
ID:   106336


Using the graphite isotope ratio method to verify the DPRK's pl / Kang, Jungmin   Journal Article
Kang, Jungmin Journal Article
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Publication 2011.
Summary/Abstract The graphite isotope ratio method can give an accurate estimate of the total plutonium production in a graphite-moderated reactor without detailed information on the reactor's operating history. Transmutation of trace impurities in the graphite is directly related to the cumulative plutonium production in the nuclear fuel. This study explains how the total amount of plutonium produced in the five megawatt electric graphite reactor at Yongbyon could be estimated using the Graphite Isotope Ratio Method (GIRM) technique once a number of strategically located samples from the graphite moderator are available.
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