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KEYWORD_EN:Embrittlement 6 result(s) found
 
1. DEVELOPMENT OF THE ALTERNATE PRESSURIZED THERMAL SHOCK RULE (10 CFR 50.61a) IN THE UNITED STATES

KIRK MARK
Nuclear Engineering and Technology, vol. 45, iss. 3, 2013, pp. 277-294
 
2. IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL

CHEN YIREN
Nuclear Engineering and Technology, vol. 45, iss. 3, 2013, pp. 311-322
 
3. RELATIONSHIP BETWEEN RADIATION INDUCTED YIELD STRENGTH INCREMENT AND CHARPY TRANSITION TEMPERATURE SHIFT IN REACTOR PRESSURE VESSEL STEELS OF KOREAN NUCLEAR POWER PLANTS

Lee, Gyeong-Geun;Lee, Yong-Bok;Kwon, Jun-Hyun;
Nuclear Engineering and Technology, vol. 44, iss. 5, 2012, pp. 543-550
 
4. MULTISCALE MODELING OF RADIATION EFFECTS ON MATERIALS: PRESSURE VESSEL EMBRITTLEMENT

Kwon, Jun-Hyun;Lee, Gyeong-Geun;Shin, Chan-Sun;
Nuclear Engineering and Technology, vol. 41, iss. 1, 2009, pp. 11-20
 
5. EVALUATION OF FAST NEUTRON FLUENCE FOR KORI UNIT 3 PRESSURE VESSEL

Yoo, Choon-Sung;Kim, Byoung-Chul;Chang, Kee-Ok;Lee, Sam-Lai;Park, Jong-Ho;
Nuclear Engineering and Technology, vol. 38, iss. 7, 2006, pp. 665-674
 
6. FUEL BEHAVIOR UNDER LOSS-OF-COOLANT ACCIDENT SITUATIONS

CHUNG HEE M.;
Nuclear Engineering and Technology, vol. 37, iss. 4, 2005, pp. 327-362
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