• Title/Summary/Keyword: 심지층처분

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Development of CANDU Spent Fuel Disposal Concepts for the Improvement of Disposal Efficiency (처분효율 향상을 위한 CANDU 사용후핵연료 처분개념 도출)

  • Lee, Jong-Youl;Cho, Dong-Geun;Kook, Dong-Hak;Lee, Min-Soo;Choi, Heui-Joo;Lee, Yang
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.7 no.4
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    • pp.229-236
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    • 2009

  • There are two types of spent fuels generated from nuclear power plants, CANDU type and PWR type. PWR spent fuels which include a lot of reusable material can be considered to be recycled. CANDU spent fuels are considered to directly disposed in deep geological formation, since they have little reusable material. In this study, based on the Korean Reference spent fuel disposal System(KRS) which is to dispose both PWR and CANDU spent fuels, the more effective CANDU spent fuel disposal systems have been developed. To do this, the disposal canister has been modified to hold the storage basket which can load 60 spent fuel bundles. From these modified disposal canisters, the disposal systems to meet the thermal requirement for which the temperature of the buffer materials should not be over $100^{\circ}C$ have been proposed. These new disposals have made it possible to introduce the concept of long tenn storage and retrievabililty and that of the two-layered disposal canister emplacement in one disposal hole. These disposal concepts have been compared and analyzed with the KRS CANDU spent fuel disposal system in terms of disposal effectiveness. New CANDU spent fuel disposal concepts obtained in this study seem to improve thermal effectiveness, U-density, disposal area, excavation volume, and closure material volume up to 30 - 40 %.

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미임계 핵변환로 최적 냉각재 선정

  • 한석중;김도형;유동한;신운철;박원석
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.690-695
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    • 1998

  • 원자력시설에서 배출되는 고준위 방사선 페기물이나 TRU 둥의 심지층처분의 보완책으로서 핵변환 (Transmutation) 처리방안이 연구되고 있다 이 핵변환시스템의 냉각재로서 액체금속류가 고려되고 있다. 본 연구에서는 핵변환로에 적합한 냉각물질을 도출하기 위해서 보다 합리적인 선정방법으로서 의사결정방법을 이용하여 중점비교 대상인 나트륨(Na), 나트륨-칼륨 합금(Na-K alloy), 납(Pb), 납-비스므스 합금(Pb-Bi alloy)에 대한 정량적 평가를 시도하였다. 아울러 이 냉각재 후보물질에 대한 냉각재로서의 적합성 여부를 비교 검토하였다. 본 방법을 이용한 결과 핵 변화로의 냉각재로서는 납-비스므스 합금이 가장 적합한 것으로 평가되었다.

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Concept of the Encapsulation Process and Equipment for the Spent Fuel Disposal (심지층 처분을 위한 사용후핵연료 포장공정 장비개념 설정)

  • Lee J.Y.;Choi H.J.;Cho D.K.;Kim S.K.;Choi J.W.;Hahn P.S.
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2005.10a
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    • pp.470-473
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    • 2005

  • Spent nuclear fuels are regarded as a high level radioactive waste and they will be disposed in a deep geological repository. To maintain the safety of the repository for hundreds of thousands of years, the spent fuels are encapsulated in a disposal canister and the canister containing spent fuels should have the structural integrity and the corrosion resistance below the several hundreds meters from the ground surface. In this study, the concept of the spent fuel encapsulation process and the process equipment fur deep geological disposal were established. To do this, the design requirements, such as the functions and the spent fuel accumulations, were reviewed. Also, the design principles and the bases were established. Based on the requirements and the bases, the encapsulation process and the equipment from spent fuel receiving process to transferring canister into the underground repository including hot cell processes was established. The established concept of the spent fuel encapsulation process and the process equipment will be improved continuously with the future studies. And this concept can be effectively used in implementing the reference repository system of our own case.

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Emplacement Process of the HLW in the Deep Geological Repository (지하처분장에서의 고준위폐기물 처분공정 개념)

  • 이종열;김성기;조동건;최희주;최종원
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2004.10a
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    • pp.1013-1016
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    • 2004

  • High level radioactive wastes, such as spent fuels generated from nuclear power plant, will be disposed in a deep geological repository. To maintain the integrity of the disposal canister and to carry out the process effectively, the emplacement process for the canister system in borehole of disposal tunnel should be well defined. In this study, the concept of the disposal canister emplacement process for deep geological disposal was established. To do this, the spent fuel arisings and disposal rate were reviewed. Also, not only design requirements, such canister and disposal depth but also preliminary repository layout concept were reviewed. Based on the requirements and the other bases, the canister emplacement process in the borehole of the disposal tunnel was established. The established concept of the disposal canister emplacement process will be improved continuously with the future studies. And this concept can be effectively used in implementing the reference repository system of our own case.

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