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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 638 - 644 (7page)
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초록· 키워드
오류제보하기
The importance of developing a source-term assessment technology has been emphasizedowing to the decommissioning of Kori nuclear power plant (NPP) Unit 1 and the increase ofdeteriorated NPPs. We analyzed the behavioral mechanism of corrosion products in theprimary system of a pressurized heavy-water reactor-type NPP. In addition, to check thepossibility of applying the CRUDTRAN code to a Canadian Deuterium Uranium Reactor(CANDU)-type NPP, the type was assessed using collected domestic onsite data. With theassessment results, it was possible to predict trends according to operating cycles. Valuesestimated using the code were similar to the measured values. The results of this study areexpected to be used to manage the radiation exposures of operators in high-radiation areasand to predict decommissioning processes in the primary system.
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등록된 정보가 없습니다.
참고문헌 (7)
참고문헌 신청
C.B. Lee / 2002 / Evaluation of CRUDTRAN code to predict transport of corrosion products and radioactivity in the PWR primary coolant system / International Conference on Water Che
D.H. Lister / 1997 / The accelerated corrosion of CANDU outlet feedersdobservations, possible mechanisms and potential remedies : 7 ~ 10
D.H. Lister / 1998 / Fuelecoolant interactions : 19 ~ 31
IAEA / 2012 / Modeling of transport of radioactive substances in the primary circuit of water-cooled reactors : 12 ~ 13
J.H. Hong / 2012 / Nuclear Materials / Hans House : 583 ~ 610
D.H. Lister / 1997 / The accelerated corrosion of CANDU outlet feedersdobservations, possible mechanisms and potential remedies : 7 ~ 10
D.H. Lister / 1998 / Fuelecoolant interactions : 19 ~ 31
IAEA / 2012 / Modeling of transport of radioactive substances in the primary circuit of water-cooled reactors : 12 ~ 13
J.H. Hong / 2012 / Nuclear Materials / Hans House : 583 ~ 610
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