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KEYWORD_EN:Uranium-molybdenum Alloy 29 result(s) found
 
1. ESTIMATIONS OF HEAT CAPACITIES FOR ACTINIDE DIOXIDE: UO<sub>2</sub>, NpO<sub>2</sub>, ThO<sub>2</sub>, AND PuO<sub>2</sub>

Eser, E.;Koc, H.;Gokbulut, M.;Gursoy, G.;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 863-868
 
2. 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
 
3. SCANNING ELECTRON MICROSCOPY ANALYSIS OF FUEL/MATRIX INTERACTION LAYERS IN HIGHLY-IRRADIATED U-Mo DISPERSION FUEL PLATES WITH Al AND Al-Si ALLOY MATRICES

Keiser, Dennis D. Jr.;Jue, Jan-Fong;Miller, Brandon D.;Gan, Jian;Robinson, Adam B.;Medvedev, Pavel;Madden, James;Wachs, Dan;Meyer, Mitch;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 147-158
 
4. IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL

Meyer, M.K.;Gan, J.;Jue, J.F.;Keiser, D.D.;Perez, E.;Robinson, A.;Wachs, D.M.;Woolstenhulme, N.;Hofman, G.L.;Kim, Y.S.;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 169-182
 
5. A MICROSTRUCTURAL MODEL OF THE THERMAL CONDUCTIVITY OF DISPERSION TYPE FUELS WITH A FUEL MATRIX INTERACTION LAYER

WILLIAMS A.F. ; LEITCH B.W. ; WANG N.
Nuclear Engineering and Technology, vol. 45, iss. 7, 2013, pp. 839-845
 
6. DEVELOPMENT OF HIGH-DENSITY U/AL DISPERSION PLATES FOR MO-99 PRODUCTION USING ATOMIZED URANIUM POWDER

RYU HO JIN ; KIM CHANG KYU ; SIM MOONSOO ; PARK JONG MAN ; LEE JONG HYUN
Nuclear Engineering and Technology, vol. 45, iss. 7, 2013, pp. 979-986
 
7. BEHAVIORS OF MOLYBDENUM IN UO<sub>2</sub> FUEL MATRIX

Ha, Yeong-Keong;Kim, Jong-Goo;Park, Yang-Soon;Park, Soon-Dal;Song, Kyu-Seok;
Nuclear Engineering and Technology, vol. 43, iss. 3, 2011, pp. 309-316
 
8. One-pot Synthesis of Dihydropyrimidinones Using Polyoxometalate Tri-supported Transition Metal Complexes

Razieh Fazaeli;Hamid Aliyan;Foroogh Mohammadifa;Amir Abbas Zamani;Mohammad Javad Bagi;
Journal of the Korean Chemical Society, vol. 55, iss. 4, 2011, pp. 666-672
 
9. LOCAL BURNUP CHARACTERISTICS OF PWR SPENT NUCLEAR FUELS DISCHARGED FROM YEONGGWANG-2 NUCLEAR POWER PLANT

Ha, Yeong-Keong;Kim, Jung-Suck;Jeon, Young-Shin;Han, Sun-Ho;Seo, Hang-Seok;Song, Kyu-Seok;
Nuclear Engineering and Technology, vol. 42, iss. 1, 2010, pp. 79-88
 
10. AN ENGINEERING SCALE STUDY ON RADIATION GRAFTING OF POLYMERIC ADSORBENTS FOR RECOVERY OF HEAVY METAL IONS FROM SEAWATER

Prasad, T.L.;Saxena, A.K.;Tewari, P.K.;Sathiyamoorthy, D.;
Nuclear Engineering and Technology, vol. 41, iss. 8, 2009, pp. 1101-1108