01472nam a2200265 c 4500001001300000005001500013008004100028040001100069041001300080052003300093245035500126300003200481545005800513545005600571545005600627653021100683700005300894700001400947700003600961773013300997856002001130900001901150900001701169900002001186KSI00011002420031230165035031203s1994    ulka          000   eng    a0110010 aengbkor01a559.105b한572ㅇㅈc26(1)00aInvestigation of the allowable transient power levels to maintain the mechanical integrity of the 17x17 KOFA fuel rod during the ANS conditions Ⅰ and Ⅱ=xANS 과도조건 Ⅰ 및 Ⅱ 에서 17x17 KOFA 핵연료봉의 기계적 건전성이 유지되는 과도상태 허용 출력준위에 관한 연구/dChan Bock Lee,eKi Hang Kim,eKyu Tae Kim  ap. 119-125:b삽도;c26 cm  aChan Bock Lee, Korea Atomic Energy Research Institute  aKi Hang Kim, Korea Atomic Energy Research Institute  aKyu Tae Kim, Korea Atomic Energy Research Institute  aANSa과도조건aKOFAa핵연료봉a연료봉a기계적a건전성a과도상태a출력준위aInvestigationaAllowableaTransientaPoweraLevelsaMaintainaMechanicalaIntegrityaFuelaRodaConditions1 a이찬복,g李讚復,d1961-0KAC2018363064aut1 a김기항1 a김규태,d1956-0KAC2013301060 t원자력학회지.d한국원자력학회.g제26권 1호(1994년 3월), p. 119-125q26:1<119w(011001)KSE199508698,x0372-732740u3207752aKd00010aLee, Chan Bock10aKim, Ki Hang10aKim, Kyu Tae태