서지주요정보
출력감발조건하에서 핵연료 피복관의 파손에 관한 연구 = A study on fuel-cladding failure under power ramping conditions
서명 / 저자 출력감발조건하에서 핵연료 피복관의 파손에 관한 연구 = A study on fuel-cladding failure under power ramping conditions / 임홍식.
발행사항 [대전 : 한국과학기술원, 1990].
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8000789

소장위치/청구기호

학술문화관(문화관) 보존서고

MNE 9017

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An attempt was made to develop a new model for analysis of the effect of power ramping rate ($\dot{P}$) on probabilities of fuel-cladding failure under power ramping conditions, although magnitude of power increase (ΔP) was generally considered as a main factor that is reponsible for cladding failure. In the present study a model expressed as a function of strain rate that is known as a parameter sensitive indirectly to power ramping rate and that influences susceptibility to stress corrosion cracking(SCC) was combined with a model related to stress. The results calculated with use of the present model were compared with experimental data(Studsvik Over-Ramp) and those computed with use of SPEAR-BETA model and PROFIT model. As power ramping rate and/or magnitude of power increase increased, failure probability also increased. It was also observed that magnitude of power increase was a primary factor and power ramping rate was a secondary factor that influences fuel-cladding failure. The present results showed a trend that was not observed with use of SPEAR-BETA model but that was similar to the trend obtained with use of PROFIT model for the effects of power ramping rate and magnitude of power increase. The effect of strain rate that correlates with power ramping rate dominated during holding period after power ramping and failure probability tended to increase during holding period. Hence the effect of strain rate during holding period seems to be correlated with the increase of SCC susceptibility although strain rate decreases during holding period. The effect of strain rate was also considered to reduce delayed failure time that is generally due to delay of iodine release and delay of increase in hoop stress by irradiation creep of Zircaloy cladding.

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서지기타정보
청구기호 {MNE 9017
형태사항 vii, 44 p. : 삽화 ; 26 cm
언어 한국어
일반주기 저자명의 영문표기 : Hong-Sik Lim
지도교수의 한글표기 : 윤용구
지도교수의 영문표기 : Young-Ku Yoon
학위논문 학위논문(석사) - 한국과학기술원 : 핵공학과,
서지주기 참고문헌 : p. 26-27
주제 Structural failures.
Nuclear fuels.
핵 연료. --과학기술용어시소러스
핵 연료체 파손. --과학기술용어시소러스
피복재. --과학기술용어시소러스
출력. --과학기술용어시소러스
Nuclear fuel claddings.
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