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KEYWORD_EN:Reactor of disinfection 127 result(s) found
 
1. CURRENT STATUS OF INTEGRITY ASSESSMENT BY SIPPING SYSTEM OF SPENT FUEL BUNDLES IRRADIATED IN CANDU REACTOR

Park, Jong-Youl;Shim, Moon-Soo;Lee, Jong-Hyeon;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 875-882
 
2. INVESTIGATION ON EFFECTS OF ENLARGED PIPE RUPTURE SIZE AND AIR PENETRATION TIMING IN REAL-SCALE EXPERIMENT OF SIPHON BREAKER

Kang, Soon Ho;Lee, Kwon-Yeong;Lee, Gi Cheol;Kim, Seong Hoon;Chi, Dae Young;Seo, Kyoungwoo;Yoon, Juhyeon;Kim, Moo Hwan;Park, Hyun Sun;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 817-824
 
3. INTEGRATED DIAGNOSTIC TECHNIQUE FOR NUCLEAR POWER PLANTS

Gofuku, Akio;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 725-736
 
4. MODAL CHARACTERISTIC ANALYSIS OF THE APR1400 NUCLEAR REACTOR INTERNALS FOR SEISMIC ANALYSIS

Park, Jong-Beom;Choi, Youngin;Lee, Sang-Jeong;Park, No-Cheol;Park, Kyoung-Su;Park, Young-Pil;Park, Chan-Il;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 689-698
 
5. A SEISMIC DESIGN OF NUCLEAR REACTOR BUILDING STRUCTURES APPLYING SEISMIC ISOLATION SYSTEM IN A HIGH SEISMICITY REGION -A FEASIBILITY CASE STUDY IN JAPAN

Kubo, Tetsuo;Yamamoto, Tomofumi;Sato, Kunihiko;Jimbo, Masakazu;Imaoka, Tetsuo;Umeki, Yoshito;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 581-594
 
6. DEVELOPMENT OF A CORE THERMO-FLUID ANALYSIS CODE FOR PRISMATIC GAS COOLED REACTORS

Tak, Nam-Il;Lee, Sung Nam;Kim, Min-Hwan;Lim, Hong Sik;Noh, Jae Man;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 641-654
 
7. DROP IMPACT ANALYSIS OF PLATE-TYPE FUEL ASSEMBLY IN RESEARCH REACTOR

Kim, Hyun-Jung;Yim, Jeong-Sik;Lee, Byung-Ho;Oh, Jae-Yong;Tahk, Young-Wook;
Nuclear Engineering and Technology, vol. 46, iss. 4, 2014, pp. 529-540
 
8. 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
 
9. EFFECTS OF TEMPERING AND PWHT ON MICROSTRUCTURES AND MECHANICAL PROPERTIES OF SA508 GR.4N STEEL

Lee, Ki-Hyoung;Jhung, Myung Jo;Kim, Min-Chul;Lee, Bong-Sang;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 413-422
 
10. PREDICTION OF THE REACTOR VESSEL WATER LEVEL USING FUZZY NEURAL NETWORKS IN SEVERE ACCIDENT CIRCUMSTANCES OF NPPS

Park, Soon Ho;Kim, Dae Seop;Kim, Jae Hwan;Na, Man Gyun;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 373-380