• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.10a
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• pp.377-378
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.205-206
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• 2016

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.289-290
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• 2012

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.1
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• pp.37-43
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• 2014

A parametric sensitivity to the annual exposure dose rate to the farming exposure group has been deterministically carried out for three principal elements identified in the near-field of the pyroprocessed waste repository system as a series study of Part 1 of the coupled paper with the same title. Credit time for both metal and ceramic containers, annual nuclide release rete and the degree of loss of bentonite buffer around the container are selected and investigated deterministically for important nuclides. To this end the A-KRS has been assessed and then compared among each other with the normal, the worst, and the best case scenarios associated with their extreme values these elements could have. All the elements are shown to be sensitive to the results as was in Part 1. Methodology studied through this study and the results are expected to make a good feedback to the repository design.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.253-253
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• 2009

전세계적 고유가 및 $CO_2$ 배출로 인한 지구 온난화 문제 동 앞으로의 에너지 개발은 지속가능하며, 환경친화적이어야 한다. 따라서 가장 값싼 에너지원의 하나이며, 또한 환경문제에서도 유리한 원자력 에너지에 대한 세계적인 관심이 지난 약 30년 정도의 침체기간을 거친후 미국, 중국, 인도, 유럽, 아시아 등을 중심으로 다시 부활하고 있다. 그러나 미래 원자력에너지의 활발한 이용 및 지속 가능성을 위해서는 고준위 방사성 폐기물의 처리문제가 반드시 해결되어야 하며, 그 중에서도 사용후핵연료의 관리문제는 원자력 발전소의 계속 운전을 위해 시급히 해결되어야 한다. 한국원자력연구원도 2008년 12월 결정된 정부의 "미래 원자력시스템 개발 Action Plan" 을 통해 이러한 사용후핵연료의 관리문제를 해결하기 위한 연구 과제를 10여년 동안 수행해오고 있으며, 그 중 하나가 파이로(Pyroprocess) 공정개발이다. 1997년부터 관련연구가 착수되어, 2001년부터는 약 6년간에 걸쳐 파이로의 전처리 공정 및 전해환원 공정에 대한 실험실 규모 실증시설인 ACPF(Advanced spent fuel Conditioning Process Facility)를 개발한 바 있다. 또한 향후 파이로 기술의 상용화를 위해 2016년 까지 약 10톤/년 규모의 공학규모 파이로 실증시설(ESPF)을 건설하고 이를 기초로 2025년까지 100톤/년 규모의 파이로 상용시설 (KAPF) 을 건설하여 여기서 나온 우라늄 및 TRU 물질을 이용해 2030년까지 개발 예정인 소듐냉각 고속로에 필요한 핵연료를 제작, 공급하는 계획을 가지고 있다. 이 논문에서는 파이로 시설개발의 가장 중요한 인자중 하나인 시설의 안전성 확보를 위해 외국 및 국내에서의 연구개발 현황을 알아보고 안전성 분석 및 평가방법에 대한 기본 인자들을 도출해 보았다. 또한 파이로 시설의 인허가를 위한 사용후핵연료 처리시설 규제관련 국, 내외의 연구현황도 알아보았다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.3
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• pp.233-244
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• 2008

A conceptual design study for a pyroprocesing facility, has been carried out in this study, which is available for the recovery of uranium and transuranic elemental group(TRU), that is, reusable as a nuclear fuel especially in a next generation-type reactor. The scale of this facility has been chosen as 20 kg HM/batch, comparatively small engineering size in order to collect scale-up data for the design of a commercial facility as well as to get operational experience. The spent fuel to be handled in this process is as follows : 3.5 % enriched uranium fuel, 35,000MWd/tU and 5-year cooled. The major items considered in the conceptual study are a building lay-out including various hot cells, safety management of the process operation in conjunction with material balance control, radiation safety, inert atmosphere control in shielded hot cells, and criticality control of uranium and TRU products.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.1
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• pp.19-35
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• 2014

A parametric sensitivity to the annual exposure dose rate to the farming exposure group has been probabilistically carried out for three principal elements associated with the nuclide transport behavior in the near-field of the pyroprocessed waste repository system. Credit time for both metal and ceramic containers, annual nuclide release rete, and the degree of loss of bentonite buffer around the container are selected as the elements and investigated for important nuclides. All the elements are shown to be sensitive to the results. Methodology studied through this study and the results are expected to make a good feedback to the repository design. As a follow-up study, separated in Part 2, the A-KRS will be deterministically assessed and then compared among each other with the normal, the worst, and the best case scenarios associated with their extreme values these elements could have.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.161-162
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• 2016

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.4
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• pp.263-272
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• 2012

A GoldSim template program for a safety assessment of a hybrid-typed repository system, called A-KRS, in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been probabilistically assessed with 9 selected input parameters, each of which has its own statistical distribution for a normal release and transport scenario associated with nuclide release and transport in and around the repository. Probabilistic dose exposure rates to the farming exposure group have been evaluated. A sensitivity of 9 selected parameters to the result has also been investigated to see which parameter is more sensitive and important to the exposure rates.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.1
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• pp.77-84
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• 2010

Reduction of oxides has been investigated for the volume reduction and recycling of the spent oxide fuel from commercial nuclear power plants. Various oxide reduction methods were proposed and KAERI (Korea Atomic Energy Research Institute) is currently developing an electrochemical reduction process using a LiCl-$Li_2O$ molten salt as a reaction medium. The electrochemical reduction process, the front end of the pyroprocessing, can connect the PWR (Pressurized Water Reactor) oxide fuel cycle to a metal fuel cycle of the sodium cooled fast reactor. This paper summarizes KAERI efforts on the development, improvement, and scale-up of the oxide reduction process.