• 제목/요약/키워드: DUPIC process

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건식 가공에 따른 DUPIC 핵연료 주기 특성

  • 김윤구;김희문;박광헌;황주호
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(3)
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    • pp.201-206
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    • 1996

  • 건식가공(Dry Process)이 사용전,후 DUPIC 핵연료의 붕괴열(Decay Heat), Hazard Index, 조사선량률(Dose Rate) 등에 미치는 영향을 계산하고, 그 원인을 분석하였다. DUPIC 사용방안으로 표준 연소도(35,000 MWD/MTU)의 경우와 장주기 연소도(50,000 MWD/MTU)의 경우를 고려하여 계산하였으며, DUPIC핵연료는 20년 냉각후 가공하는 것을 기준으로 하였다. 또한 DUPIC핵연료 장전시 고려할 수 있도록 사용전 DUPIC 핵연료에 대한 계산을 핵연료 집합체(Bundle) 단위로 하였다. 조사선량과 붕괴열은 건식가공에 상당히 민감한 반응을 보였고 이는 주로 Cs의 제기에 의한 것이다.

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DUPIC 핵연료의 조사선량률 분석 (Source Intensity Analysis of DUPIC Fuel)

  • 김윤구;임재용;박범락;박광헌;황주호
    • Journal of Radiation Protection and Research
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    • 제21권2호
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    • pp.117-124
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    • 1996

  • 사용전 그리고 사용후 DUPIC핵연료의 선원분석을 연료다발에서 1m떨어진 지점의 조사선량률을 기준으로하여 분석하였다. BUPIC핵연료 제조에 사용된 PWR핵연료는 표준 연소도와 장주기 연소도를 갖는 것으로 설정하였고, 건식 가공에서 제거되는 핵분열생성물의 양을 고려하여 두 가지의 경우를 고려하였다. 조사선량률은 균일 혼합체 모형을 사용하여 구하였다. 조사선량률 값은 매우 크게 나왔으며. 건식가공 중의 Cs제거율에 민감하게 변화하는 것으로 나타났다. 10년 이상 냉각된 PWR핵연료를 사용한 DUPIC핵연료의 경우 핵연료 내 모든 Cs을 제거하면 약 90% 이상의 조사선량률을 감소시킬 수 있다. 조사선량률에 주된 영향을 미치는 주요 방사선원은 Cs-137이다. Cs제거에 관련된 연구는 DUPIC핵연료의 조사선량 뿐만 아니라. 건식 처리시설의 방사성 물질 관리에도 중요하다.

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DUPIC 핵연료봉 봉단 용접부 건전성 확인을 위한 미세초점 X-선 투과시험에 관한 연구 (A Study on the Micro-Focus X-Ray Inspection for Confirming the Soundness of End Closure Weld of DUPIC Fuel Elements)

  • 김웅기;김수성;이정원;양명승
    • Journal of Welding and Joining
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    • 제19권1호
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    • pp.88-94
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    • 2001

  • DUPIC (Direct use of spent PWR fuel in CANDU reactors) nuclear fuel is a CANDU fuel fabricated remotely from spent PWR fuel materials in a hot cell. The soundness of the end closure welds of nuclear fuel elements is an important factor for the safety and performance of nuclear fuel. To evaluate the soundness of the end closure welds of DUPIC fuel element, a precise X-ray inspection system is developed using a micro-focus X-ray generator with an image intensifier and a real time camera system. The fuel elements made of Zircaloy-4 and stainless steel by an Nd:YAG laser welding and a TIG welding aye inspected by the developed inspection system. The soundness of the welds of the fuel elements was confirmed by the X-ray inspection process, and the irradiation test of DUPIC fuel elements has been successfully completed at the HANARO research reactor.

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모의 DUPIC 핵연료의 소결 특성 연구 (A Study on the Sintering of Simulated DUPIC Fuel)

  • 강권호;배기광;박희성;송기찬;문제선
    • 한국분말재료학회지
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    • 제7권3호
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    • pp.123-130
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    • 2000

  • The simulated DUPIC fuel provides a convenient way to investigate fuel properties and behaviours such as thermal conductivity, thermal expansion, fission gas release, leaching and so on. Several pellets simulating the composition and microstructure of the DUPIC fuel were fabricated from resintering powder through the OREOX process of the simulated spent fuel pellets, which were prepared from the mixture of stable forms of constituent nuclides. This study describes the powder treatment, OREOX, compaction and sintering to fabricate simulated DUPIC fuel using the simulated spent fuel. The homogeneity of additives in the powder was observed after attrition milling. The microstructure of the simulated spent fuel was in agreement with the previous studies. The densities and the grain size of simulated DUPIC fuel was pellets are higher than those of simulated spent fuel pellets. Small metallic precipitates and oxide precipitates were observed on matrix grain boundaries.

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Recent Progress of the DUPIC Fuel Fabrication in Korea

  • Lee, J.W.;Kim, W.K.;Lee, Jae-W.;Park, G.I.;YANG, M.S.
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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    • pp.170-181
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    • 2004

  • DUPIC powder and pellets were successfully fabricated in accordance with the quality assurance program described in the Quality Assurance Manual for DUPIC fuel fabrication, which was developed on the basis of the CAN3-Z299.2-85 standard. This manual describes the quality management system applicable to the activities performed for DUPIC fuel fabrication. It covers the work processes, policies and procedures used for planning, executing, and verifying the work carried out for DUPIC fuel fabrication. It is important that a Quality Program is in place before the fabrication of the fuel for irradiation testing. In order to qualify the DUPIC pellet manufacturing processes, 3 series of experiments for the pre-qualification and 3 series for the qualification were performed. In these experiments, the optimum process conditions were established. Then, under the control of the QA program, 8 series of production runs were performed to make the qualified DUPIC pellets in a batch size of 1 kg. In these production runs, DUPIC fuel pellets satisfying the standard CANDU fuel pellet specifications could be successfully produced.

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