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KEYWORD_EN:Fuel Cycle
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1. Future Urban Transportation Technologies for Sustainability with an Emphasis on Growing Mega Cities: A Strategic Proposal on Introducing a New Micro Electric Vehicle Segment
Honey, Emilio;Lee, Hojin;Suh, In-Soo;
World Technopolis Review, vol. 3, iss. 3, 2014, pp. 139-152
Honey, Emilio;Lee, Hojin;Suh, In-Soo;
World Technopolis Review, vol. 3, iss. 3, 2014, pp. 139-152
2. DEVELOPMENT OF LEAD SLOWING DOWN SPECTROMETER FOR ISOTOPIC FISSILE ASSAY
Lee, YongDeok;Park, Chang Je;Ahn, Sang Joon;Kim, Ho-Dong;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 837-846
Lee, YongDeok;Park, Chang Je;Ahn, Sang Joon;Kim, Ho-Dong;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 837-846
3. 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
Park, Jong-Youl;Shim, Moon-Soo;Lee, Jong-Hyeon;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 875-882
4. HEAT-UP AND COOL-DOWN TEMPERATURE-DEPENDENT HYDRIDE REORIENTATION BEHAVIORS IN ZIRCONIUM ALLOY CLADDING TUBES
Won, Ju-Jin;Kim, Myeong-Su;Kim, Kyu-Tae;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 681-688
Won, Ju-Jin;Kim, Myeong-Su;Kim, Kyu-Tae;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 681-688
5. 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
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
6. SHIELDING ANALYSIS OF DUAL PURPOSE CASKS FOR SPENT NUCLEAR FUEL UNDER NORMAL STORAGE CONDITIONS
Ko, Jae-Hun;Park, Jea-Ho;Jung, In-Soo;Lee, Gang-Uk;Baeg, Chang-Yeal;Kim, Tae-Man;
Nuclear Engineering and Technology, vol. 46, iss. 4, 2014, pp. 547-556
Ko, Jae-Hun;Park, Jea-Ho;Jung, In-Soo;Lee, Gang-Uk;Baeg, Chang-Yeal;Kim, Tae-Man;
Nuclear Engineering and Technology, vol. 46, iss. 4, 2014, pp. 547-556
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
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. PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
Cabellos, O.;Castro, E.;Ahnert, C.;Holgado, C.;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 299-312
Cabellos, O.;Castro, E.;Ahnert, C.;Holgado, C.;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 299-312
9. NUCLEAR DATA UNCERTAINTY AND SENSITIVITY ANALYSIS WITH XSUSA FOR FUEL ASSEMBLY DEPLETION CALCULATIONS
Zwermann, W.;Aures, A.;Gallner, L.;Hannstein, V.;Krzykacz-Hausmann, B.;Velkov, K.;Martinez, J.S.;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 343-352
Zwermann, W.;Aures, A.;Gallner, L.;Hannstein, V.;Krzykacz-Hausmann, B.;Velkov, K.;Martinez, J.S.;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 343-352
10. REVIEW OF 15 YEARS OF HIGH-DENSITY LOW-ENRICHED UMo DISPERSION FUEL DEVELOPMENT FOR RESEARCH REACTORS IN EUROPE
Van Den Berghe, S.;Lemoine, P.;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 125-146
Van Den Berghe, S.;Lemoine, P.;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 125-146