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KEYWORD_EN:code pseudo range 39 result(s) found
 
1. DEVELOPMENT OF A COMPUTER PROGRAM TO SUPPORT AN EFFICIENT NON-REGRESSION TEST OF A THERMAL-HYDRAULIC SYSTEM CODE

Lee, Jun Yeob;Suh, Jaeseung;Kim, Kyung Doo;Jeong, Jae Jun;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 719-724
 
2. RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS

Yoon, Han Young;Lee, Jae Ryong;Kim, Hyungrae;Park, Ik Kyu;Song, Chul-Hwa;Cho, Hyoung Kyu;Jeong, Jae Jun;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 655-666
 
3. THE INVESTIGATION OF BURNUP CHARACTERISTICS USING THE SERPENT MONTE CARLO CODE FOR A SODIUM COOLED FAST REACTOR

Korkmaz, Mehmet E.;Agar, Osman;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 407-412
 
4. DEVELOPMENT AND VALIDATION OF A NUCLEAR FUEL CYCLE ANALYSIS TOOL: A FUTURE CODE

KIM S. K. ; KO W. I. ; LEE YOON HEE
Nuclear Engineering and Technology, vol. 45, iss. 5, 2013, pp. 665-674
 
5. TAPINS: A THERMAL-HYDRAULIC SYSTEM CODE FOR TRANSIENT ANALYSIS OF A FULLY-PASSIVE INTEGRAL PWR

LEE YEON-GUN ; PARK GOON-CHERL
Nuclear Engineering and Technology, vol. 45, iss. 4, 2013, pp. 439-458
 
6. ON THE MODELLING OF TWO-PHASE FLOW IN HORIZONTAL LEGS OF A PWR

Bestion, D.;Serre, G.;
Nuclear Engineering and Technology, vol. 44, iss. 8, 2012, pp. 871-888
 
7. MONITORING SEVERE ACCIDENTS USING AI TECHNIQUES

No, Young-Gyu;Kim, Ju-Hyun;Na, Man-Gyun;Lim, Dong-Hyuk;Ahn, Kwang-Il;
Nuclear Engineering and Technology, vol. 44, iss. 4, 2012, pp. 393-404
 
8. COMPARATIVE ANALYSIS OF STATION BLACKOUT ACCIDENT PROGRESSION IN TYPICAL PWR, BWR, AND PHWR

Park, Soo-Yong;Ahn, Kwang-Il;
Nuclear Engineering and Technology, vol. 44, iss. 3, 2012, pp. 311-322
 
9. FUEL PERFORMANCE CODE COSMOS FOR ANALYSIS OF LWR UO<sub>2</sub> AND MOX FUEL

Lee, Byung-Ho;Koo, Yang-Hyun;Oh, Jae-Yong;Cheon, Jin-Sik;Tahk, Young-Wook;Sohn, Dong-Seong;
Nuclear Engineering and Technology, vol. 43, iss. 6, 2011, pp. 499-508
 
10. APPLICATIONS OF INTEGRATED SAFETY ANALYSIS METHODOLOGY TO RELOAD SAFETY EVALUATION

Jang, Chan-Su;Um, Kil-Sup;
Nuclear Engineering and Technology, vol. 43, iss. 2, 2011, pp. 187-194