Influence of a temperature change on in-reactor creep
Description
The results of a series of pressurized tube creep experiments, conducted in Experimental Breeder Reactor II (EBR-II), were evaluated to determine the effect of a temperature change on the in-reactor creep of AISI Type 316 stainless steel. In contrast to prior breeder reactor experiments where a temperature change was imposed and only a short interval of additional fluence accumulated prior to examination, this experiment examines the long-term effects of a temperature change. Data are reported from three separate experiments in which the temperature history was altered by a linear reduction with fluence, a step increase and a step decrease. Analysis of the data indicated that the long-term creep rate adjusts to the new temperature. However, evidence of swelling and stress-affected swelling resulting from the temperature change were found
Additional details
Publishing Information
- Publisher
- American Society for Testing Materials.
- Imprint Place
- Philadelphia, PA (USA)
- Imprint Title
- Effects of radiation on materials
- Journal Page Range
- p. 38-51.
Conference
- Title
- 12. international symposium on effects of radiation on materials.
- Dates
- 18-20 Jun 1984.
- Place
- Williamsburg, VA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17051858
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; DAMAGING NEUTRON FLUENCE; EBR-2 REACTOR; IRRADIATION; MECHANICAL TESTS; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; STEEL-CR17NI12MO3; SWELLING; TEMPERATURE DEPENDENCE; THERMAL STRESSES
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STE; CORROSION RESISTANT ALLOYS; DEFORMATION; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NEUTRON FLUENCE; NICKEL ALLOYS; POWER REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEELS; STRESSES; TESTING