Creep-Fatigue Effects in Structural Materials used in Advanced Nuclear Power Generating Systems
- 1 January 1983
- book chapter
- Published by Springer Nature
Abstract
No abstract availableKeywords
This publication has 9 references indexed in Scilit:
- High-temperature fatigue life of type 316 stainless steel containing irradiation induced heliumJournal of Nuclear Materials, 1981
- Effect of environment on crack growth behavior in austenitic stainless steels under creep and fatigue conditionsMetallurgical Transactions A, 1980
- Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environmentJournal of Nuclear Materials, 1979
- The effect of oxidation on hol time fatigue behavior of 2.25 Cr-1 Mo steelMetallurgical Transactions A, 1979
- Estimates of Time-Dependent Fatigue Behavior of Type 316 Stainless Steel Subject to Irradiation Damage in Fast Breeder and Fusion Power Reactor SystemsPublished by ASTM International ,1979
- Mechanical Properties of Liquid-Metal Fast Breeder Reactor Primary Piping MaterialsNuclear Technology, 1977
- Time-dependent strain-controlled fatigue behavior of annealed 2 14 Cr-1 Mo steel for use in nuclear steam generator designJournal of Nuclear Materials, 1976
- Some Questions Regarding the Interaction of Creep and FatigueJournal of Engineering Materials and Technology, 1976
- The effect of high vacuum on the low cycle fatigue lawMetallurgical Transactions, 1972