-
4
-
-
85046796156
-
Spannungsrisskorrosion von Stählen für Reaktorkomponenten in Heisswasser
-
February
-
H.P. Seifert, J. Heldt, U. Ineichen, B. Tirbonod, U. Tschanz, "Spannungsrisskorrosion von Stählen für Reaktorkomponenten in Heisswasser", BFE-Schlussbericht, February 2000.
-
(2000)
BFE-Schlussbericht
-
-
Seifert, H.P.1
Heldt, J.2
Ineichen, U.3
Tirbonod, B.4
Tschanz, U.5
-
7
-
-
33751082225
-
Strain induced corrosion cracking of low-alloy reactor pressure vessel steels under BWR conditions
-
(CD-ROM, Paper No.3), August 6-10 Lake Tahoe, Nevada, USA
-
th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE/TMS/ANS, (CD-ROM, Paper No.3), August 6-10, 2001, Lake Tahoe, Nevada, USA.
-
(2001)
th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE/TMS/ANS
-
-
Seifert, H.P.1
Ritter, S.2
-
11
-
-
29144438859
-
Strain-induced corrosion cracking of low-alloy steels under BWR conditions: Are there still open issues?
-
(CD-ROM, Paper No.156), August 6-10 Lake Tahoe, Nevada, USA
-
th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE/TMS/ANS, (CD-ROM, Paper No.156), August 6-10, 2001, Lake Tahoe, Nevada, USA.
-
(2001)
th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE/TMS/ANS
-
-
Hickling, J.1
-
13
-
-
0343584839
-
The critical cracking potential of RPV steel in pressurized high temperature water
-
Moskau, UDSSR
-
rd IAEA Specialists Meeting on Subcritical Crack Growth, NUREG/CP-0112, Vol. 2, pp. 109-116, Moskau, UDSSR, 1990.
-
(1990)
rd IAEA Specialists Meeting on Subcritical Crack Growth, NUREG/CP-0112
, vol.2
, pp. 109-116
-
-
Shoji, T.1
-
14
-
-
0021548432
-
-
J. Congleton, T. Shoji, R.N. Parkins, Corrosion Science, Vol.25, 1985, pp. 633-650.
-
(1985)
Corrosion Science
, vol.25
, pp. 633-650
-
-
Congleton, J.1
Shoji, T.2
Parkins, R.N.3
-
16
-
-
33745190369
-
Effects of dynamic strain aging on environment-assisted cracking of low-alloy pressure vessel and piping steels
-
(CD-ROM, Paper No. 47), August 6-10 Lake Tahoe, Nevada, USA
-
th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE/TMS/ANS, (CD-ROM, Paper No. 47), August 6-10, 2001, Lake Tahoe, Nevada, USA.
-
(2001)
th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE/TMS/ANS
-
-
Hänninen, H.1
-
17
-
-
0242566629
-
-
E.D. Eason, E.E. Nelson, J.D. Gilman, Nuclear Engineering & Design, Vol.184, 1998, pp. 89-111.
-
(1998)
Nuclear Engineering & Design
, vol.184
, pp. 89-111
-
-
Eason, E.D.1
Nelson, E.E.2
Gilman, J.D.3
-
19
-
-
84909660379
-
Cyclic crack growth studies for predicting crack growth in the HDR thermal shock experiments
-
nd IAEA Specialsist's Meeting on Subcritical Crack Growth, NUREG/CP-0067, Vol. 2, pp. 431-453.
-
nd IAEA Specialsist's Meeting on Subcritical Crack Growth, NUREG/CP-0067
, vol.2
, pp. 431-453
-
-
Gerscha, A.1
Klausnitzer, E.2
Blind, D.3
Jansky, J.4
Rintamaa, R.5
Saario, T.6
Törrönen, K.7
-
20
-
-
0004675413
-
-
ASME XI Appendix A-4300 Appendix A, Article A-4000, Subsection A-4300: Fatigue Crack Growth Rate" ASME, New York
-
ASME XI Appendix A-4300, 1998 ASME Boiler & Pressure Vessel Code, Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, Appendix A, Article A-4000, Subsection A-4300: Fatigue Crack Growth Rate" ASME, New York 1998.
-
(1998)
1998 ASME Boiler & Pressure Vessel Code, Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components
-
-
-
21
-
-
0029350411
-
-
E.D. Eason, E.E. Nelson, J.D. Gilman, Welding Research Council Bulletin, Vol.404, 1995, pp. 38-51.
-
(1995)
Welding Research Council Bulletin
, vol.404
, pp. 38-51
-
-
Eason, E.D.1
Nelson, E.E.2
Gilman, J.D.3
|