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KEYWORD_EN:APR1400 17 result(s) found
 
1. DESIGN OF A VIBRATION AND STRESS MEASUREMENT SYSTEM FOR AN ADVANCED POWER REACTOR 1400 REACTOR VESSEL INTERNALS COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM

KO DO-YOUNG ; KIM KYU-HYUNG
Nuclear Engineering and Technology, vol. 45, iss. 2, 2013, pp. 249-256
 
2. ANALYSIS OF THE ISP-50 DIRECT VESSEL INJECTION SBLOCA IN THE ATLAS FACILITY WITH THE RELAP5/MOD3.3 CODE

Sharabi, Medhat;Freixa, Jordi;
Nuclear Engineering and Technology, vol. 44, iss. 7, 2012, pp. 709-718
 
3. VIBRATION AND STRESS ANALYSIS OF A UGS ASSEMBLY FOR THE APR1400 RVI CVAP

Ko, Do-Young;Kim, Kyu-Hyung;
Nuclear Engineering and Technology, vol. 44, iss. 7, 2012, pp. 817-824
 
4. A SUMMARY OF 50<sup>th</sup> OECD/NEA/CSNI INTERNATIONAL STANDARD PROBLEM EXERCISE (ISP-50)

Choi, Ki-Yong;Baek, Won-Pil;Kang, Kyoung-Ho;Park, Hyun-Sik;Cho, Seok;Kim, Yeon-Sik;
Nuclear Engineering and Technology, vol. 44, iss. 6, 2012, pp. 561-586
 
5. INTERNATIONAL STANDARD PROBLEM 50: THE UNIVERSITY OF PISA CONTRIBUTION

Cherubini, Marco;Lazzerini, Davide;Giannotti, Walter;D`auria, Francesco;
Nuclear Engineering and Technology, vol. 44, iss. 6, 2012, pp. 587-596
 
6. MAJOR THERMAL-HYDRAULIC PHENOMENA FOUND DURING ATLAS LBLOCA REFLOOD TESTS FOR AN ADVANCED PRESSURIZED WATER REACTOR APR1400

Park, Hyun-Sik;Choi, Ki-Yong;Cho, Seok;Kang, Kyoung-Ho;Kim, Yeon-Sik;
Nuclear Engineering and Technology, vol. 43, iss. 3, 2011, pp. 257-270
 
7. DEVELOPMENT OF AN IMPROVED INSTALLATION PROCEDURE AND SCHEDULE OF RVI MODULARIZATION FOR APR1400

Ko, Do-Young;
Nuclear Engineering and Technology, vol. 43, iss. 1, 2011, pp. 89-98
 
8. A PARTICLE TRACKING MODEL TO PREDICT THE DEBRIS TRANSPORT ON THE CONTAINMENT FLOOR

Bang, Young-Seok;Lee, Gil-Soo;Huh, Byung-Gil;Oh, Deog-Yeon;Woo, Sweng-Woong;
Nuclear Engineering and Technology, vol. 42, iss. 2, 2010, pp. 211-218
 
9. CORE THERMAL HYDRAULIC BEHAVIOR DURING THE REFLOOD PHASE OF COLD-LEG LBLOCA EXPERIMENTS USING THE ATLAS TEST FACILITY

Cho, Seok;Park, Hyun-Sik;Choi, Ki-Yong;Kang, Kyoung-Ho;Baek, Won-Pil;Kim, Yeon-Sik;
Nuclear Engineering and Technology, vol. 41, iss. 10, 2009, pp. 1263-1274
 
10. THE DESIGN FEATURES OF THE ADVANCED POWER REACTOR 1400

Lee, Sang-Seob;Kim, Sung-Hwan;Suh, Kune-Yull;
Nuclear Engineering and Technology, vol. 41, iss. 8, 2009, pp. 995-1004