• Title/Summary/Keyword: PWR 사용후핵연료

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MOX 연료주기의 경제성분석

  • 문기환
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05b
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    • pp.1087-1092
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    • 1995

  • MOX 연료는 PWR, BWR, FBR 및 ATR 등과 같은 다양한 노형에서 이용이 가능하다. 이와 같은 MOX 연료는 이미 일부 국가에서 이들 노형에 이용하고 있으며, FBR의 상용화 시기가 다소 지연될 것으로 예상되어 이 분야에 대찬 연구는 더욱 활발히 진행될 전망이다. 여기에서는 이와 같은 현실을 감안하여 MOX 연료를 이용하는 MOX 연료주기와 우라늄 연료만을 이용하는 우라늄 연료주기에 대한 핵연료주기비를 비교·분석하였고, 그 결과 MOX 연료주기와 우라늄 연료주기의 경제성은 거의 대둥한 것으로 평가되었다. 또한 우라늄 가격, 사용후핵연료 처분시기, 처분 비용/재처리비용 등의 주요 변수에 대한 민감도분석을 수행한 결과, MOX 연료주기가 우라늄연료주기에 대해 상당한 경쟁력을 가지고 있는 것으로 분석되었다.

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A Study on the Dissolution and Separation for the Quantitative Analysis of Iodide in Spent Nuclear Fuel (사용후핵연료중의 미량 요오드 정량을 위한 용해 및 분리 연구)

  • Choi, Ke Chon;Lee, Chang Heon;Song, Byang Chol;Park, Yang Soon;Jee, Kwang Yong;Kim, Won Ho
    • Analytical Science and Technology
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    • v.13 no.6
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    • pp.751-758
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    • 2000

  • A study was carried out on the dissolution of spent PWR fuels and performed on the fuels and the separation of iodide for the quantitative analysis using SIMFUEL which has chemical composition of a simulated spent PWR fuel (burn-up; 35,000 MWd/MTU and cooling time; 10 years). To dissolve the SIMFUEL effectively and to minimize the formation of volatile iodine through dissolution process, the optimum ratio of mixed acid ($HNO_3/HCl$ 80: 20 mol%) was established and ozone gas was purged. In the separation step of iodine with $CCl_4$, $NH_2OH{\cdot}HCl$ was used for reducing ${IO_3}^-$ to $I_2$.The optimum acidity of the dissolved solution and the added of $NH_2OH{\cdot}HCl$ were 2.5 M and more than $1.5{\times}10^{-3}mole$, respectively. The recovery of iodide by ion chromatography was $82.8{\pm}4.1%$ and the total yield was corrected by gamma spectrometery using $^{131}I$ as a tracer.

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An Analysis of the Deep Geological Disposal Concepts Considering Spent Fuel Rods Consolidation (사용후핵연료봉 밀집을 고려한 심지층처분 개념 분석)

  • Lee, Jongyoul;Kim, Hyeona;Lee, Minsoo;Kim, Geonyoung;Choi, Heuijoo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.4
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    • pp.287-297
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    • 2014

  • For several decades, many countries operating nuclear power plants have been studying the various disposal alternatives to dispose of the spent nuclear fuel or high-level radioactive waste safely. In this paper, as a direct disposal of spent nuclear fuels for deep geological disposal concept, the rod consolidation from spent fuel assembly for the disposal efficiency was considered and analyzed. To do this, a concept of spent fuel rod consolidation was described and the related concepts of disposal canister and disposal system were reviewed. With these concepts, several thermal analyses were carried out to determine whether the most important requirement of the temperature limit for a buffer material was satisfiedin designing an engineered barrier of a deep geological disposal system. Based on the results of thermal analyses, the deposition hole distance, disposal tunnel spacing and heat release area of a disposal canister were reviewed. And the unit disposal areas for each case were calculated and the disposal efficiencies were evaluated. This evaluation showed that the rod consolidation of spent nuclear fuel had no advantages in terms of disposal efficiency. In addition, the cooling time of spent nuclear fuels from nuclear power plant were reviewed. It showed that the disposal efficiency for the consolidated spent fuel rods could be improved in the case that cooling time was 70 years or more. But, the integrity of fuels and other conditions due to the longer term storage before disposal should be analyzed.

  • https://doi.org/10.7733/jnfcwt.2014.12.4.287 인용 PDF KSCI KPUBS HTML