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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

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

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

BREVET 2.271.169 (A2) (7514982). - 14 MAI 1975. PROCEDE ET APPAREIL POUR LA PRODUCTION DE GAZ PAR COMBUSTION INCOMPLETE D'HYDROCARBURES.sdPatent

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

Plutonium et combustible MOXLes Cahiers de Global chance. 2013, Num 34, pp 12-13, issn 1270-377X, 2 p.Article

Raman and XPS characterization of fuel-cladding interactions using miniature specimensWINDISCH, C. F; HENAGER, C. H; ENGELHARD, M. H et al.Journal of nuclear materials. 2009, Vol 383, Num 3, pp 237-243, issn 0022-3115, 7 p.Article

Options for the long-term management of separated plutoniumNUTTALL, William J; FARNAN, Ian; HAMILTON, David J et al.Progress in nuclear energy (New series). 2007, Vol 49, Num 8, issn 0149-1970, 85 p.Conference Proceedings

Measurement of uranium-238 Doppler effect in a nitride fueled LMFBR at FCAANDOH, M; OKAJIMA, S; OIGAWA, H et al.Journal of Nuclear Science and Technology. 1999, Vol 36, Num 4, pp 386-388, issn 0022-3131Article

Melting temperature of irradiated fast reactor mixed oxide fuelsKONNO, K; HIROSAWA, T.Journal of Nuclear Science and Technology. 1998, Vol 35, Num 7, pp 494-501, issn 0022-3131Article

Some investigations and developments of the thorium fuel cycleTROYANOV, M. F; ILYUNIN, V. G; KALASHNIKOV, A. G et al.Atomic energy (New York, N.Y.). 1998, Vol 84, Num 4, pp 225-229, issn 1063-4258Article

Transport calculations of MOX and UO2 pin cells by the method of characteristicsPETKOV, P. T; TAKEDA, T.Journal of Nuclear Science and Technology. 1998, Vol 35, Num 12, pp 874-885, issn 0022-3131Article

Détermination par diffraction des rayons X de la distribution en composition des solutions solides U1-yCeyO2dans un composite UO2-U1-yCeyO2 = X ray diffraction study of distribution of solid U1-yCeyO2 solutions in UO2-U1-yCeyO2BUISSON, P; PILUSO, P; PERNET, M et al.Journal de physique. IV. 1998, Vol 8, Num 5, pp 77-84, issn 1155-4339Conference Paper

Nuclear design study on a super high-burnup fuel assembly for pressurized water reactors using transuraniumMORI, M; HIJIYA, M; SHIROYA, S et al.Journal of Nuclear Science and Technology. 1997, Vol 34, Num 7, pp 644-654, issn 0022-3131Article

Void coefficient analysis of an LWR lattice experiment with high-enrichment MOX fuelBÖHME, R; BERGER, H.-D; CHAWLA, R et al.Nuclear engineering and design. 1997, Vol 168, Num 1-3, pp 271-279, issn 0029-5493Article

Analyses of boiling water reactor mixed-oxide critical experiments with CASMO-4/SIMULATE-3SAJI, E; SHIRAYANAGI, H.Nuclear science and engineering. 1995, Vol 121, Num 1, pp 52-56, issn 0029-5639Article

Les stratégies d'emploi du plutonium à long terme : Le plutonium = Strategies of plutonium use at long termBARRE, B; BOUCHARD, J.Revue générale nucléaire. 1995, Num 1, pp 58-59, issn 0335-5004Article

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