• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.11a
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• pp.225-226
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• 2006

본 논문에서는 PWR 사용후핵연료의 처분용기를 원가대상으로 단위당 제조원가를 추정하였다. 추정결과, 처분용기의 내부는 구상흑연주철로 외부는 순동판으로 후판 제작하였을 경우, KDC-1 처분용기의 단위당 제조원가는 약 2억 3천만원으로 추정되었다. 또한 외부용기를 순동 주물로 제조하였을 경우는 단위당 제조원가가 약 2억 1천만원으로 추정되었다. 그리고 외부용기를 후판제작 할 경우, 총 제조원가 대비 각 제조원가의 2대 요소별로 비율을 살펴보면, 직접재료비는 38%, 직접 노무비 50%, 제조간접비 12%로 추정되었다. 따라서 한국형처분장 개념설계에서 36,000tU을 처분하는데 소요되는 처분용기 14,210개중 PWR 처분용기 11,375개를 고려하였을 경우, 처분용기 총 원가는 사용후핵연료 처분 총 원가의 주요한 원가동인임을 확인하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.94.1-94
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.90.2-90
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• 2001

• Proceedings of the Korean Powder Metallurgy Institute Conference
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• 2002.04b
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• pp.33-34
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• 2002

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2012.05a
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• pp.1019-1020
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• 2012

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.67-67
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.345-345
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.312.2-312
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• 1999

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.4
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• pp.335-344
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• 2006

In this paper a computer program was developed, which simulates the Li reduction process of PWR spent fuel, and the amount of a produced metal or chloride compound was calculated at the various amount of Li with the program. It establishes a database, which is composed of some characteristics related to a chemical reaction equation and thermodynamic data, and it calculates the transformed rate of PWR spent fuel oxide at the certain amount of Li by using the database as input data. As the results of the performance test of the program, it was validated that the transformed values of oxides, except for $Eu_2O_3$ and $Sm_2O_3$, were almost the same to within about a 6 % error with those calculated by the previous code and that the calculated amount of Li was also exactly consistent with the theoretical one, which is used for a complete reaction of each oxide in a single chemical reaction. A relationship between Li and the transformed metal of each oxide was analyzed on the basis of the quantities calculated with the verified development program. Of the results, when the amount of Li was given to be 250 mole, the 83.73 percentage of $UO_2$ was transformed into U while the remainder was still to be $UO_2$. In addition, it was appeared that the 297 mole of Li was needed to completely convert $UO_2$ into U.

• Journal of Radiation Protection and Research
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• v.37 no.4
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• pp.197-201
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• 2012

Annual dose at the boundary of the interim storage facility at normal condition was calculated to estimate the site area of the facility of PWR spent nuclear fuel. In this work, source term was generated by ORIGEN-ARP for 4.5 wt% initial enrichment, 45,000 MWd/MTU burnup and 10 years cooling time. Modeling of the storage facilities and radiation shielding evaluations were conducted by MCNP code depending on the storage capacity. In the case of the centralized storage system, the required site area was found to have the radius of more than 700 m.