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Analysis on Lift-Off experiment in Halden reactor by FEMAXI-6 codeSUZUKI, M; KUSAGAYA, K; SAITOU, H et al.Journal of nuclear materials. 2004, Vol 335, Num 3, pp 417-424, issn 0022-3115, 8 p.Article

Accident scenarios of the TRIGA Mark II reactor in ViennaVILLA, Mario; HAYDN, Markus; STEINHAUSER, Georg et al.Nuclear engineering and design. 2010, Vol 240, Num 12, pp 4091-4095, issn 0029-5493, 5 p.Article

A new method to study hydriding processes from the inner surfaces of fuel claddingsSACEDON, J. L; DIAZ, M; MOYA, J. S et al.Journal of nuclear materials. 2004, Vol 327, Num 1, pp 11-18, issn 0022-3115, 8 p.Article

Development of the ultra-microhardness technique for post irradiation examination of fuel cladding tubesNAKATSUKA, M; NOMATA, T; UMEHARA, H et al.Journal of Nuclear Science and Technology. 1998, Vol 35, Num 5, pp 344-352, issn 0022-3131Article

Electrically conducting paths in thick (>10 μm) zirconia filmsCOX, B; WONG, Y.-M; HOANG, T et al.Journal of nuclear materials. 1995, Vol 223, Num 2, pp 202-209, issn 0022-3115Article

Mechanical design issues and resolutions of a dual cooled fuel for the OPR-1000KIM, Hyung-Kyu; KIM, Jae-Yong; YOON, Kyung-Ho et al.Nuclear engineering and design. 2011, Vol 241, Num 6, pp 2119-2127, issn 0029-5493, 9 p.Article

Chemical reactions of caesium, tellurium and oxygen with fast breeder reactor cladding alloys. VII: The kinetics of the corrosion od 12R72HV steel by Cs2Te at at constant O2 potential; comparison with rates for PE16 alloyPULHAM, R. J; RICHARDS, M. W.Journal of nuclear materials. 1995, Vol 223, Num 2, pp 180-185, issn 0022-3115Article

Effect of hydride orientation on fracture toughness of Zircaloy-4 claddingHSU, Hsiao-Hung; TSAY, Leu-Wen.Journal of nuclear materials. 2011, Vol 408, Num 1, pp 67-72, issn 0022-3115, 6 p.Article

A review on the clad failure studiesALAM, Tanweer; KALEEM KHAN, Mohd; PATHAK, Manabendra et al.Nuclear engineering and design. 2011, Vol 241, Num 9, pp 3658-3677, issn 0029-5493, 20 p.Article

Anisotropic swelling observed during stress-free reirradiation of AISI 304 tubes previously irradiated under stressGARNER, F. A; FLINN, J. E; HALL, M. M et al.Journal of nuclear materials. 2009, Vol 386-88, pp 249-253, issn 0022-3115, 5 p.Conference Paper

Zirconium oxidation at low temperature and pressure (comments on a paper by X. Iltis et al., J. Nucl. Mater. 209 (1994) 180)COX, B.Journal of nuclear materials. 1995, Vol 218, Num 2, pp 261-264, issn 0022-3115Article

Lanthanides migration and immobilization in U-Zr nuclear fuelsBOZZOLO, G; HOFMAN, G. L; YACOUT, A. M et al.Journal of nuclear materials. 2012, Vol 425, Num 1-3, pp 188-192, issn 0022-3115, 5 p.Conference Paper

MEASUREMENT OF TRITIUM DURING VOLOXIDATION OF ZIRCALOY-2 CLADDINGCROWDER, Mark L; LAURINAT, James E; STILLMAN, John A et al.Nuclear technology. 2011, Vol 176, Num 2, pp 309-313, issn 0029-5450, 5 p.Article

Microstructure evolution in Zr1Nb fuel cladding during high-temperature oxidationNEGYESI, M; BLAHOVA, O; ADAMEK, J et al.Journal of nuclear materials. 2011, Vol 416, Num 3, pp 298-302, issn 0022-3115, 5 p.Article

Kinetic studies of the α―β phase transition in the Zr1%Nb cladding for nuclear reactorsBENES, O; VAN UFFELEN, P; VAN DE LAAR, J et al.Journal of nuclear materials. 2011, Vol 414, Num 2, pp 88-91, issn 0022-3115, 4 p.Conference Paper

Analyses of operational transients in the TRADE experimental programGABRIELLI, F; D'ANGELO, A.Nuclear engineering and design. 2009, Vol 239, Num 11, pp 2349-2356, issn 0029-5493, 8 p.Article

Mechanical response of oxidized Zircaloy-4 cladding material submitted to a ring compression testBUSSER, Vincent; BAIETTO-DUBOURG, Marie-Christine; DESQUINES, Jean et al.Journal of nuclear materials. 2009, Vol 384, Num 2, pp 87-95, issn 0022-3115, 9 p.Article

Model of cladding failure estimation for a cycling nuclear unitMAKSIMOV, M. V; PELYKH, S. N; MASLOV, O. V et al.Nuclear engineering and design. 2009, Vol 239, Num 12, pp 3021-3026, issn 0029-5493, 6 p.Article

A model based on bootstrapped neural networks for computing the maximum fuel cladding temperature in an Rmbk-1500 nuclear reactor accidentCADINI, F; ZIO, E; KOPUSTINSKAS, V et al.Nuclear engineering and design. 2008, Vol 238, Num 9, pp 2165-2172, issn 0029-5493, 8 p.Article

Measurement of the Young modulus anisotropy of a reactor pressure vessel claddingVANDERMEULEN, W; SCIBETTA, M; LEENAERS, A et al.Journal of nuclear materials. 2008, Vol 372, Num 2-3, pp 249-255, issn 0022-3115, 7 p.Article

Effect of radial hydrides on the axial and hoop mechanical properties of Zircaloy-4 claddingCHU, H. C; WU, S. K; CHIEN, K. F et al.Journal of nuclear materials. 2007, Vol 362, Num 1, pp 93-103, issn 0022-3115, 11 p.Article

Thermodynamic evaluation of the Nb-O-Zr systemJERLERUD PEREZ, R; MASSIH, A. R.Journal of nuclear materials. 2007, Vol 360, Num 3, pp 242-254, issn 0022-3115, 13 p.Article

Some factors involved in the development of a tubular process for Nb3Sn conductorsGREGORY, E; ZEITLIN, B. A; TOMSIC, M et al.IEEE transactions on applied superconductivity. 2007, Vol 17, Num 2, pp 2664-2667, issn 1051-8223, 4 p., 3Conference Paper

Optimization of uranium dioxide structure for use in the fuel elements of a thermionic converter reactorGONTAR, A. S; GRIDNEV, A. A; RAKITSKAYA, E. M et al.Atomic energy (New York, N.Y.). 2005, Vol 99, Num 4, pp 702-705, issn 1063-4258, 4 p.Article

Measurements of hydrogen permeation and absorption in zirconium oxide scalesBYUNG HYUCK LIM; HYUN SEON HONG; KYUNG SUB LEE et al.Journal of nuclear materials. 2003, Vol 312, Num 2-3, pp 134-140, issn 0022-3115, 7 p.Article

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