• 방사성폐기물학회지
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• 제5권4호
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• pp.351-357
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• 2007

일본 정부는 사용후핵연료의 중간저장시설의 입지로 아우모리현의 무쯔시를 선정했다. 2000년부터 시작된 유치활동이 5 년만에 결실을 맺은 것이다. 한국은 사용후핵연료를 원자력 발전소 내에 저장하고 있는데 2016년이면 저장한계에 이를 것으로 전망되고 있어 일본의 사례연구는 한국에 시사하는 바가 크다. 한국은 경주에 중, 저준위 방사성 폐기물 저장시설을 성공적으로 유치한 경험이 있어 사용후핵연료의 저장시설을 유치하는 학습경험을 축적한 바 있는데 두 나라의 큰 차이점은 한국은 경쟁적인 주민투표를 통하면서 막대한 지역지원금을 지원한다는 점이고 일본은 주민투표를 시행하지 않고 지방자치 정치의 리더쉽이 문제를 해결하는 방식을 택했다는 점이다. 엄청난 지역지원금이 지원되지 않은 점도 일본의 특징이다. 본 연구가 한국의 사용후핵 연료 저장시설을 유치하는 데 도움이 되었으면 하는 바람이다.

• Nuclear Engineering and Technology
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• 제42권3호
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• pp.237-248
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• 2010

The safety of metal cask and concrete cask storage technology has been verified by CRIEPI through several research programs on demonstrative testing for the interim storage of spent fuel. The results have been reflected in the safety requirements for dry casks issued by NISA/METI (Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry) of the Japanese government. On top of that, spent fuel integrity has been studied by the Japan Nuclear Energy Safety Organization (JNES). This paper reviews these research programs. Future issues include the long-term integrity of cask components and high burn-up spent fuel.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.380-380
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• 1998

• 방사선산업학회지
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• 제18권1호
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• pp.35-42
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• 2024

Demand for RW transportation is expected to increase due to the continuous generation of RW from nuclear power plants and facilities, decommissioning of plants, and saturation of spent fuel temporary storage facilities. The locational aspect of plants and radiation protection optimization for the public have led to an increasing demand for maritime transportation, necessitating to apprehend the overseas and domestic current status. Given the potential long-term radiological impact on the public in the event of a sinking accident, a pre-transportation exposure assessment is necessary. The objective of this study is to investigate the overseas and domestic RW maritime transportation current status and overseas dose assessment cases for the public in sinking accident. Selected countries, including Japan, UK, Sweden, and Korea, were examined for transport cases, Japan and the U.S were chosen for dose assessment case in sinking accidents. As a result of the maritime transportation case analysis, it was performed between nuclear power plants and reprocessing facilities, from plants to disposal or intermediate storage facilities. HLW and MOX fuel were transported using INF 3 shipments, and all transports were performed low speed of 13 kn or less. As a result of the dose assessment for the public in sinking accident, japan conducted an assessment for the sinking of spent fuel and vitrified HLW, and the U.S conducted for the sinking of spent fuel. Both countries considered external exposure through swimming and working at seashore, and internal exposure through seafood ingestion as exposure pathway. Additionally, Japan considered external exposure through working on board and fishing, and the U.S considered internal exposure through spray inhalation and desalinized water and salt ingestion. Internal exposure through seafood ingestion had the largest dose contribution. The average public exposure dose was 20 years after the sinking, 0.04 mSv yr^-1 for spent fuel and 5 years after the sinking, 0.03 mSv yr^-1 for vitrified HLW in Japan. In the U.S, it was 1.81 mSv yr^-1 5 years after the sinking of spent fuel. The results of this study will be used as fundamental data for maritime transportation of domestic RW in the future.

• Nuclear Engineering and Technology
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• 제45권1호
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• pp.115-124
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• 2013

Among the several options to solve PWR spent fuel accumulation problem in Korea, the dry storage method could be the most realistic and applicable solution in the near future. As the basic objectives of dry storage are to prevent a gross rupture of spent fuel during operation and to keep its retrievability until transportation, at the same time the importance of a spent fuel integrity evaluation that can estimate its condition at the final stage of dry storage is very high. According to the national need and technology progress, two representative nations of spent fuel dry storage, the USA and Japan, have established different system temperature criteria, which is the only controllable factor in a dry storage system. However, there are no technical criteria for this evaluation in Korea yet, it is necessary to review the previously well-organized methodologies of advanced countries and to set up our own domestic evaluation direction due to the nation's need for dry storage. To satisfy this necessity, building a domestic spent fuel test database should be the first step. Based on those data, it is highly recommended to compare domestic data range with foreign results, to build our own criteria, and to expand on evaluation work into recently issued integrity problems by using a comprehensive integrity evaluation code.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2339-2358
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• 2022

The review discusses various alternative approaches for spent nuclear fuel (SNF) reprocessing in aqueous carbonate media. The main stages, schemes, and methods of the most well-known and well-described processes for reprocessing SNF and some high-level radioactive waste using carbonate systems developed by research groups in Japan, the United States of America, the Republic of Korea, and the Russian Federation described and compared. The main advantages of such methods are outlined compared to the SNF reprocessing in nitric acid media. The levels of development and proximity of the designed processes to the industrial implementation are shown. The main principle achievements, prospects, and routes for the refinement of such methods for the technology of SNF reprocessing and handling of high-level radioactive waste formulated.

• 전기저널
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• 통권415호
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• pp.62-66
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• 2011

• 방사성폐기물학회지
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• 제11권4호
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• pp.333-349
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• 2013

최근 국내에서도 원전 부지 내에 건설된 습식저장조의 용량이 곧 포화될 것으로 예상되어 사용후핵연료의 건식저장에 관한 논의가 활발하다. 이 논문에서는 앞으로 다양하게 논의될 저장시스템의 안전성과 함께 장기 건식저장 시 발생하는 사용후핵연료의 특성 및 건전성 변화에 대해 이제까지 국내외에서 연구 보고된 내용들을 면밀히 검토하고 향후 추구해야 할 연구방향을 제시하고자 하였다. 조사 결과 건식저장 기간 동안 진행될 수 있는 여러 피복관 열화기구 중에서 가장 대표적인 기구는 크립 변형과 수소화물에 의한 영향이었으며, 이들이 사용후핵연료 장기 건식저장 시 규제기술기준의 주요 근간을 이루고 있는 것으로 분석되었다. 한편 과거에는 피복관의 크립 변형이 가장 중요한 열화기구로 평가되었으나, 최근의 연구 결과를 통해 수소화물에 의한 영향이 더 심각한 것으로 드러났고 이는 미국의 규제기준과 새로운 온도 범위를 제시하고 있는 일본의 규제기준에서 확인할 수 있었다. 그러나, 아직까지 수소화물에 의한 영향이 발생하는 응력과 온도 조건을 명확히 규명할 수 있는 연구 자료가 충분하지 못하며, 나아가 사용후핵연료의 취급 시 거동에 대한 연구도 지속적으로 수행해야 할 부분으로 드러났다. 따라서 국내 사용후핵연료 특성에 맞는 건식저장조건을 수립하기 위해서는 국내에서도 본격적인 연구를 통해 이들 자료에 대한 충분한 생산과 평가 및 분석이 뒤따라야 할 것으로 판단된다.

• 방사성폐기물학회지
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• 제21권3호
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• pp.383-395
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• 2023

Since 1997, the Republic of Korea (ROK) has been developing pyro-processing (Pyro) technology to reduce the disposal burden of high-level radioactive waste by recycling spent nuclear fuel (SNF). Compared to plutonium and uranium extraction process, Korean Pyro technology has relatively excellent proliferation resistance that cannot separate pure plutonium owing to its intrinsic characteristics. Regarding Pyro technology development of ROK, the Bush administration considered that Pyro is not reprocessing under the Global Nuclear Energy Partnership, whereas the Obama administration considered that Pyro is subject to reprocessing. However, the Bush and Obama administrations did not allow ROK to conduct full Pyro activities using SNF, even though ROK had faithfully complied with international nonproliferation obligations. This is because the US nuclear nonproliferation policy to prevent the spread of sensitive technologies, such as enrichment and reprocessing, has a strong effect on ROK, unlike Japan, on a bilateral level beyond the NPT regime for non-proliferation of nuclear weapons.

• Nuclear Engineering and Technology
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• 제44권5호
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• pp.459-470
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• 2012

From the PSA point of view, the Fukushima accident of Japan in 2011 reveals some issues to be re-considered and/or improved in the PSA such as the limited scope of the PSA, site risk, etc. KAERI (Korea Atomic Energy Research Institute) has performed researches on the development of an integrated risk assessment framework related to some issues arisen after the Fukushima accident. This framework can cover the internal PSA model and external PSA models (fire, flooding, and seismic PSA models) in the full power and the low power-shutdown modes. This framework also integrates level 1, 2 and 3 PSA to quantify the risk of nuclear facilities more efficiently and consistently. We expect that this framework will be helpful to resolve the issue regarding the limited scope of PSA and to reduce some inconsistencies that might exist between (1) the internal and external PSA, and (2) full power mode PSA and low power-shutdown PSA models. In addition, KAERI is starting researches related to the extreme external events, the risk assessment of spent fuel pool, and the site risk. These emerging issues will be incorporated into the integrated risk assessment framework. In this paper the integrated risk assessment framework and the research activities on the emerging issues are outlined.