• Tunnel and Underground Space
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• v.11 no.2
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• pp.132-145
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• 2001

The purpose and need of the study is to quantify the advantage or disadvantage of the environmental friendliness of the partitioning of nuclear fuel cycle. To this end, a preliminary study on the quantitative effect of the partition on the permanent disposal of spent PWR and CANDU fuel (HLW) was carried out. Before any analysis, the so-called reference radionuclide release scenario from a potential repository embedded into a crystalline rock was developed. Firstly, the feature, event and processes (FEPs) which lead to the release of nuclides from waste disposed of in a repository and the transport to and through the biosphere were identified. Based on the selected FEPs, the ‘Well Scenario’which might be the worst case scenario was set up. For the given scenario, annual individual doses to a local resident exposed to radioactive hazard were estimated and compared to that from direct disposal. Even though partitioning and transmutation could be an ideal solution to reduce the inventory which eventually decreases the release time as well as the peaks in the annual dose and also minimize the repository area through the proper handling of nuclides, it should overcome major disadvantages such as echnical issues on the partitioning and transmutation system, cost, and public acceptance, and environment friendly issues. In this regard, some relevant issues are also discussed to show the direction for further studies.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.2
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• pp.195-202
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• 2018

As a rule, geological disposal is considered a safe method for final disposal of high-level radioactive waste. However, some long-lived fission products like $^{99}Tc$ and $^{129}I$ contained in spent nuclear fuel are highly mobile as less sorbing anionic species in the subsurface environment and can mainly cause exposure dose to the ecosystem by emission of beta rays in the hundreds of keV range. Therefore, if these two nuclides can be separated and converted with high efficiency into radioactively unharmful nuclides, this would have a positive effect on disposal safety. One candidate method is to transmute these two nuclides in nuclear reactors into short-lived nuclides or into stable nuclides. For this purpose, it is necessary to evaluate which reactor type is more efficient in burning these two nuclides. In this study, the simulation results of nuclear transmutation of $^{99}Tc$ and $^{129}I$ in light water reactor (PWR), heavy water reactor (CANDU) and fast neutron reactor (SFR, MET-1000) are compared and discussed.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 1997.10a
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• pp.32-37
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• 1997

안전조치 측면에서 관심의 대상이 되어온 중수형 원전의 건식저장고 및 사용후 핵연료 이송 검증을 위한 안전조치 접근방법이 국가 계량관리 검사의 이행을 위하여 개발되었다. 이는 IAEA 사찰장비를 활용하지 못하는 우리나라의 현실을 반영하여 자체 개발된 비파괴검증장비가 이용되며, IAEA 안전조치 기준을 만족시킬 것으로 기대된다. 건식저장고에 대한 국가 계량관리 검사기준은 자체 개발된 비파괴검증장비와 봉인에 의존하는 기준이 제안되었으며, 검증활동은 시설운영자의 부담경감을 위하여 IAEA 사찰이 실시되는 기간동안 동시에 실시되도록 되어 있다. Transfer campaign 검증을 위하여 3명의 국가 계량관리 검사관이 검증활동에 참여하게 되며, 이를 통하여 이송작업의 연속성 유지 및 시설운영자의 부담경감 등이 달성됨과 함께 사참량의 감소가 기대된다. 본 논문은 국가 계량관리 검사의 시작과 함께 현실적인 어려움을 극복하면서, IAEA의 안전조치 기준을 만족하는 안전조치 접근방법을 제시하고 있으며, 안전조치 목적을 보다 적합하게 달성할 것으로 기대된다.