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Results 1 to 25 of 98

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Metal corrosion studies with the fluorosulphonic acid-antimony pentafluoride superacid systemELLER, P. Gary; KISSANE, Richard J; ABNEY, Kent D et al.Journal of alloys and compounds. 2004, Vol 365, pp 134-137, issn 0925-8388, 4 p.Article

Computer simulation of early-stage irradiation creepNAGAKAWA, J; YAMAMOTO, N; SHIRAISHI, H et al.Journal of nuclear materials. 1991, Vol 179-81, Num B, pp 986-989, issn 0022-3115Conference Paper

Quantification of brittle-ductile failure behavior of ferritic reactor pressure vessel steels using the Small-Punch-Test and micromechanical damage modelsLINSE, T; KUNA, M; VIEHRIG, H.-W et al.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2014, Vol 614, pp 136-147, issn 0921-5093, 12 p.Article

Oxide microstructures of advanced Zr alloys corroded in 360 °C water loopPARK, Jeong-Yong; SEUNG JO YOO; CHOI, Byung-Kwon et al.Journal of alloys and compounds. 2007, Vol 437, Num 1-2, pp 274-279, issn 0925-8388, 6 p.Article

Influence of cyclic strain rate on environmentally assisted cracking behavior of pressure vessel steel in high-temperature waterWU, X. Q; KATADA, Y.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2004, Vol 379, pp 58-71, issn 0921-5093, 14 p.Article

Effects of strain rate and temperature on tensile behavior of hydrogen-charged SA508 Cl.3 pressure vessel steelWU, X. Q; KIM, I. S.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2003, Vol 348, Num 1-2, pp 309-318, issn 0921-5093, 10 p.Article

Crack-Arrest testing of irradiated nuclear reactor pressure vessel Steels at the Oak Ridge National LaboratoryISKANDER, S. K; MILELLA, P. P; PINI, A et al.Journal of testing and evaluation. 1998, Vol 26, Num 6, pp 546-554, issn 0090-3973Article

Determination of chemical activities of Fe, Cr, Ni and Mn in stainless steel 316 by Knudsen effusion cell mass spectrometryVENUGOPAL, V; KULKARNI, S. G; SUBBANNA, C. S et al.Journal of alloys and compounds. 1995, Vol 218, Num 1, pp 95-100, issn 0925-8388Article

Metallurgical evaluation of stress corrosion cracking in large diameter pipingWHEELER, D. A; RAWL, D. E; LOUTHAN, M. R et al.Materials characterization. 1994, Vol 32, Num 1, pp 25-33, issn 1044-5803Conference Paper

A position-sensitive atom probe approach to characterization of Al2O3 dispersion strengthened Cu alloySHA, W; ZHU, F.Journal of nuclear materials. 1992, Vol 186, Num 3, pp 288-293, issn 0022-3115Article

Residual strain in a fusion reactor first-wall component subjected to thermal fatigueALBERTINI, G; ANDRE, G; MATERA, R et al.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 1991, Vol 148, Num 2, pp 211-217, issn 0921-5093Article

Study of cyclic radiation and thermal effects on material for diverter plates of thermonuclear reactorBYSTROV, L. N; IVANOV, L. I; MARKUSHEV, V. L et al.Fizika i himiâ obrabotki materialov. 1991, Num 4, pp 38-42, issn 0015-3214Article

Development of 9Cr-ODS ferritic-martensitic steel prepared by chemical reduction and mechanical millingSUN, Q. X; ZHOU, Y; FANG, Q. F et al.Journal of alloys and compounds. 2014, Vol 598, pp 243-247, issn 0925-8388, 5 p.Article

Ion-irradiation effects on dissimilar friction stir welded joints between ODS alloy and ferritic stainless steelCHEN, C.-L; RICHTER, A; KÖGLER, R et al.Journal of alloys and compounds. 2014, Vol 615, issn 0925-8388, S448-S453, SUP1Conference Paper

Effect of hydrogen on the slip resistance of tungsten single crystalsYAO, W. Z; WANG, P; MANHARD, A et al.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2013, Vol 559, pp 467-473, issn 0921-5093, 7 p.Article

Neutron diffraction measurement of residual stresses in CFC/Cu/CuCrZr joints for nuclear fusion technologyFIORI, F; CALBUCCI, V; CASALEGNO, V et al.Journal of physics. Condensed matter (Print). 2008, Vol 20, Num 10, issn 0953-8984, 104260.1-104260.6Conference Paper

Effects of strength mis-matching on the fracture behavior of nuclear pressure steel A508-III welded jointZHENGQIANG ZHU; HONGYANG JING; JINGGUO GE et al.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2005, Vol 390, Num 1-2, pp 113-117, issn 0921-5093, 5 p.Article

Microstructure of a reactor pressure vessel steel close to the zones of ductile tearing and cleavageKARLIK, M; NEDBAL, I; SIEGL, J et al.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2003, Vol 357, Num 1-2, pp 423-428, issn 0921-5093, 6 p.Article

Thermographic investigation of the fatigue behavior of reactor pressure vessel steelsYANG, B; LIAW, P. K; WANG, H et al.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2001, Vol 314, Num 1-2, pp 131-139, issn 0921-5093Conference Paper

Nondestructive evaluation of irradiation effects in RPV steel using Barkhausen noise and magnetoacoustic emission signalsPARK, D. G; OK, C. I; JEONG, H. T et al.Journal of magnetism and magnetic materials. 1999, Vol 196-97, pp 382-384, issn 0304-8853Conference Paper

A remotely operated FIMEC apparatus for the mechanical characterization of neutron irradiated materialsDONATO, A; GONDI, P; MONTANARI, R et al.Journal of nuclear materials. 1998, Vol 258263, pp 446-451, issn 0022-3115, aConference Paper

The change of Barkhausen noise due to thermal ageing in Inconel 600PARK, D. G; KIM, S. S; AHN, B. G et al.Journal de physique. IV. 1998, Vol 8, Num 2, pp Pr2.797-Pr2.800, issn 1155-4339Conference Paper

Size and geometry effects on ductile rupture of notched bars in a C-Mn steel: experiments and modellingDECAMP, K; BAUVINEAU, L; BESSON, J et al.International journal of fracture. 1997, Vol 88, Num 1, pp 1-18, issn 0376-9429Article

Effect of loading mode on the fracture toughness of a reduced-activation ferritic/martensitic stainless steelHUAXIN LI; JONES, R. H; HIRTH, J. P et al.Journal of nuclear materials. 1994, Vol 212-15, Num A, pp 741-745, issn 0022-3115Conference Paper

Localized corrosion studies on materials proposed for a safety-grade sodium-to-air decay-heat removal system for fast breeder reactorsKAMACHI MUDALI, U; KHATAK, H. S; DAYAL, R. K et al.Journal of materials engineering and performance. 1993, Vol 2, Num 1, pp 135-140, issn 1059-9495Article

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