• Title, Summary, Keyword: PWR

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Corrosion Fatigue Characteristics of CF8M and CF8A on the PWR Condition (PWR환경에서 CF8M, CF8A 배관재의 부식피로특성 연구)

  • Jeong, Ill-Seok;Lee, Yong-Sung;Kim, Sang-Jai;Song, Taek-Ho;Cho, Sun-Young
    • Proceedings of the KSME Conference
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    • pp.1062-1067
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    • 2003
  • In this study, corrosion fatigue characteristics of CF8M and CF8A steel were investigated on the simulated PWR condition(Temp.:$316^{\circ}C$, Pres.: 15:MPa). To make the simulated PWR condition. the special test machine consisted of INSTRON, Autoclave, LOOP and Measurement system was developed. As ${\Delta}K$ is ranged from 11 to $20MPa{\sqrt{m}}$, Crack growth rate of PWR condition is faster than air condition. Above $20MPa{\sqrt{m}}$, the crack growth rate of PWR and air condition is similar. Corrosion fatigue characteristics regardless of the ferrite contents($10{\sim}25wt.%$) is not different. After the test, the fracture surface of specimens was examined. It was difficult to verify the fracture modes such as striation, intergranular crack and cleavage and so on. As the ferrite content of CF8M is increased, the more particles covered fracture surface were peeled.

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사용후핵연료 금속저장체의 열해석 평가

  • 이주찬;신영준;민덕기;노성기
    • Proceedings of the Korean Nuclear Society Conference
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    • pp.476-481
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    • 1998
  • 본 연구에서는 PWR 핵연료집합체를 금속 전환시켜 형성된 금속저장체에 대한 온도분포를 계산하였다. 해석모델은 PWR 핵연료집합체 2개 및 4개를 1개의 금속저장체로 전환한 경우로 하였다. PWR 핵연료를 금속 전환할 경우 금속전환 과정에서 Sr과 Cs를 선택적으로 제거함으로서 냉각부하를 약 1/2로 줄일 수 있고 체적을 약 1/4로 줄일 수 있는 잇점이 있다. 열해석 결과 2 PWR 핵연료 금속저장체에서 저장시스템 주변 공기의 온도가 50 $^{\circ}C$ 인 경우, 금속 연료봉의 최고온도는 164 $^{\circ}C$로 나타났다. 또한, 4 PWR 핵연료 금속저장체의 경우 금속 연료봉의 최고온도는 사각형 저장체에서 193 $^{\circ}C$, 육각형 저장체에서 183 $^{\circ}C$ 로 나타났다. 따라서 건식 저장에서 연료봉의 온도를 낮게 하기 위해서는 저장 밀도를 높일 수 있는 연료봉 밀집화 (rod consolidation) 방식이 경제성 측면뿐만 아니라 열안전성 측면에서도 유리한 것으로 나타났다.

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Nuclear Characteristics of a New(PWR-PHWR) Fuel Cycle (PWR-PHWR 핵연료 주기의 핵적 특성)

  • Jae Woong Song;Chang Hyun Chung
    • Nuclear Engineering and Technology
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    • v.17 no.3
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    • pp.185-192
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    • 1985
  • The fissile content of PWR spent fuel is higher than that of natural uranium which is normal fuel for CANDU type reactor. Investigated are the concepts of PWR spent fuel utilization in CANDU type reactor to diversify uranium resource and partially to solve storage problems of PWR spent fuel being gradually accumulated. Nuclear characteristics of uranium-plutonium mixed oxide fuel loaded in CANDU type reactor are analysed using the WIMS/D computer code. In this study, analyses are solely carried out upon the current CANDU type reactor design without changingany reactivity control devices.

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