Transmutation of MA in the high flux thermal reactorBIN LIU; WENCHAO HU; KAI WANG et al.Journal of nuclear materials. 2013, Vol 437, Num 1-3, pp 95-101, issn 0022-3115, 7 p.Article

Low-temperature properties of mixed diesel fuelsAZEV, V. S; PRIVALENKO, A. N; SHARIN, E. A et al.Chemistry and technology of fuels and oils. 2001, Vol 37, Num 2, pp 103-106, issn 0009-3092Article

Thermal conductivity of homogeneous and heterogeneous MOX fuel with up to 44 MWd/kgHM burn-upSTAICU, D; COZZO, C; PAGLIOSA, G et al.Journal of nuclear materials. 2011, Vol 412, Num 1, pp 129-137, issn 0022-3115, 9 p.Article

Design of a gadolinia bearing mixed-oxide fuel assembly for pressurized water reactorsYAMATE, K; MORI, M; USHIO, T et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 35-51, issn 0029-5493Conference Paper

Optimization of a calculation scheme for the treatment of plutonium recycling in pressurized water reactorsFOUGERAS, P; CATHALAU, S; MONDOT, J et al.Nuclear science and engineering. 1995, Vol 121, Num 1, pp 32-40, issn 0029-5639Article

MOx benchmark calculations by deterministic and Monte Carlo codes : Selected and expanded papers from International Conference Nuclear Energy for New Europe 2010, Portoroz, Slovenia, September 6-9, 2010PECCHIA, M; KOTEV, G; PARISI, C et al.Nuclear engineering and design. 2012, Vol 246, pp 63-68, issn 0029-5493, 6 p.Article

Market prospectsOUTRAM, Robert.Petroleum review (London. 1968). 2006, Vol MAR, pp 38-39, issn 0020-3076, 2 p., SUPArticle

Ignition of a binary-fuel(solvent-solute) cluster of dropsBELLAN, J; HARSTAD, K.Combustion science and technology. 1995, Vol 110/11, pp 531-550, issn 0010-2202, 18 p.Article

Wavelet-based angular dependence analysis of the heterogeneous calculation on MOX fuel latticeYOUQI ZHENG; HONGCHUN WU; LIANGZHI CAO et al.Nuclear engineering and design. 2009, Vol 239, Num 10, pp 1804-1810, issn 0029-5493, 7 p.Article

Estimation of oxygen potential for U―Pu―O mixed oxide fuelVANA VARAMBAN, S; GANESAN, V; VASUDEVA RAO, P. R et al.Journal of nuclear materials. 2009, Vol 389, Num 1, pp 72-77, issn 0022-3115, 6 p.Conference Paper

Alternative configurations for the QUADRISO fuel design conceptTALAMO, Alberto; POUCHON, Manuel A; VENNERI, Francesco et al.Journal of nuclear materials. 2009, Vol 383, Num 3, pp 264-266, issn 0022-3115, 3 p.Article

Oxygen chemical diffusion in hypo-stoichiometric MOXKATO, Masato; MORIMOTO, Kyoichi; TAMURA, Tetsuya et al.Journal of nuclear materials. 2009, Vol 389, Num 3, pp 416-419, issn 0022-3115, 4 p.Article

Structural studies of the phase separation in the UO₂―PuO₂―Pu₂O₃ ternary systemTRUPHEMUS, Thibaut; BELIN, Renaud C; ROGEZ, Jacques et al.Journal of nuclear materials. 2013, Vol 432, Num 1-3, pp 378-387, issn 0022-3115, 10 p.Article

Some considerations of the performance of small dual fuel furnaces fueled with a gaseous fuel and a liquid fuel mix containing used engine lube oilAL OMARI, S.-A. B; ABU-JDAYIL, B.Renewable energy. 2013, Vol 56, pp 117-122, issn 0960-1481, 6 p.Conference Paper

International congress on advanced nuclear power plants (ICAPP). Special-Part 2Nuclear technology. 2004, Vol 145, Num 3, issn 0029-5450, 88 p.Conference Proceedings

NOUVELLES METHODES DE CO-CONVERSION PAR VOIE AQUEUSE DE L'URANIUM (IV) ET DU PLUTONIUM(IV) POUR PREPARER DES OXYDES MIXTES (U, PU)O₂ EN VUE DE LA FABRICATION DE COMBUSTIBLES MOX = NEW METHODS FOR CO-CONVERSION OF URANIUM(IV) AND PLUTONIUM(IV) IN AQUEOUS MEDIUM TO PREPARE MIXTES OXIDES (U, PU)O₂ FOR MOX FUELSMesmin, Claire; Madic, Charles.2000, 235 p.Thesis

Acceleration of the Analytic function expansion nodal method by two-factor two-node nonlinear iterationKAP SUK MOON; NAM ZIN CHO; JAE MAN NOH et al.Nuclear science and engineering. 1999, Vol 132, Num 2, pp 194-202, issn 0029-5639Article

Cogema et la gestion du plutonium militaire = Cogema and its management of military plutoniumDE MONTALEMBERT, A.Revue générale nucléaire. 1999, Num 4, pp 29-31, issn 0335-5004Article

Studies of nuclear materials recycling in conventional and advanced reactorsGUILLET, J. L; GROUILLER, J. P.TopFuel '99. International topical meetingSFEN /ENS conference. 1999, pp 248-255Conference Paper

Effective utilization of weapon-grade plutonium to upgrade repeatedly-reprocessed mixed-oxide fuel for use in pressurized water reactorsHANAYAMA, Y; YAMAMOTO, A; KANDA, K et al.Journal of Nuclear Science and Technology. 1999, Vol 36, Num 9, pp 746-754, issn 0022-3131Article

L'exportation de combustible nucléaire = The export of nuclear fuelPEYRAN, J.-C.Revue générale nucléaire. 1998, Num 4, pp 99-101, issn 0335-5004Article

Development of fresh fuel packaging for ATR demonstration reactorOUCHI, Y; YAMANAKA, R; KURAKAMI, J et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 1738-1743, 4VolConference Paper

Transport and storage of MOX fuels methodology for criticality assessment methodsGUILLOU, E; LEJEUNE, E; AGUIAR, L et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 1829-1833, 4VolConference Paper

The development of BNFL's MOX fuel supply businessEDWARDS, J; BROWN, C; MARSHALL, S. J et al.International nuclear conference on recycling, conditioning and disposal. 1998, pp 182-190, 3VolConference Paper

Kostenvorteile durch Wiederaufarbeitung : Konditionierung und Recyklierung = Reprocessing-Conditioning-Recycling : A competitive industry at the service of the utilitiesGIRAUD, J.-P; DEVEZEAUX DE LAVERGNE, J.-G.Atw. Atomwirtschaft, Atomtechnik. 1997, Vol 42, Num 5, pp 303-306, issn 0365-8414Article