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Céramiques dans les réacteurs électro-nucléaires à eau pressurisée = Ceramics in nuclear pressurized water reactorsBERNARDIN, M.L' Industrie céramique (Paris). 1990, Num 850, pp 433-435, issn 0019-9044, 3 p.Article

Present status of fast breeder reactor fuel cycle development at PNCYAMAMOTO, M; MATSUMOTO, K.-I.Nuclear technology. 1990, Vol 89, Num 2, pp 194-202, issn 0029-5450, 9 p.Article

Modified pyrohydrolysis apparatus for the separation of fluorine and chlorine trace impurities from nuclear fuel samples for quality control analysisMAHAJAN, M. A; PRASAD, M. V. R; MHATRE, H. R et al.Journal of radioanalytical and nuclear chemistry. 1991, Vol 148, Num 1, pp 93-100, issn 0236-5731, 8 p.Article

Controlled potential coulometric determination of plutonium in mixed (U,Pu) carbide fuelsHAR SWROOP SHARMA; KHEDEKAR, N. B; MARATHE, S. G et al.Nuclear technology. 1990, Vol 89, Num 3, pp 399-405, issn 0029-5450, 7 p.Article

Evaluation of the mixed-oxide fuel melting limit at low burnupsKOMODA, S; HOSOKAWA, T; KINJO, K et al.Kerntechnik (1987). 1990, Vol 55, Num 2, pp 112-116, issn 0932-3902, 5 p.Article

Nuclear fuel reprocessing of (U, Pu)O2 fuelINOUE, A.Nuclear technology. 1990, Vol 90, Num 2, pp 186-190, issn 0029-5450, 5 p.Article

The grain growth of mixed oxide fuel during irradiationBRAINBRIDGE, J. E; FORTY, C. B. A; MARTIN, D. G et al.Journal of nuclear materials. 1990, Vol 171, Num 2-3, pp 230-236, issn 0022-3115, 7 p.Article

Longitudinal ultrasonic velocity in plutonium-uranium carbide (0.7Pu-O.3U)C pelletsPANAKKAL, J. P.Journal of nuclear materials. 1990, Vol 172, Num 1, pp 135-137, issn 0022-3115, 3 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

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

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

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

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

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

Performance of direct alcohol fuel cells fed with mixed methanol/ethanol solutionsWONGYAO, N; THERDTHIANWONG, A; THERDTHIANWONG, S et al.Energy conversion and management. 2011, Vol 52, Num 7, pp 2676-2681, issn 0196-8904, 6 p.Article

Development of the SESAME metallic fuel performance codeKOBAYASHI, T; KINOSHITA, M; HATTORI, S et al.Nuclear technology. 1990, Vol 89, Num 2, pp 183-193, issn 0029-5450, 11 p.Article

Measurements of the total pressure from irradiated (U,Pu)-mixed oxideBREITUNG, W; WRIGHT, S. A.Nuclear science and engineering. 1990, Vol 105, Num 4, pp 303-318, issn 0029-5639, 16 p.Article

Non-destructive determination of plutonium in nuclear fuel rods and pelletsPILZ, N; HOFFMANN, P; LIESER, K. H et al.Fresenius' Zeitschrift für analytische Chemie. 1989, Vol 335, Num 7, pp 695-697, issn 0016-1152, 3 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

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