Neutron and deuteron irradiation creep in stainless steel alloys
Creators
- 1. Commission of the European Communities, Petten (Netherlands). Joint Nuclear Research Center
- 2. Commission of the European Communities, Ispra (Italy). Joint Research Centre
Description
Irradiation rigs have been developed for HFR in Petten in which 49 specimens at a time can be irradiated in uniaxial tension. The creep elongations of AMCR type steels and of 20% cold-worked US 316 stainless steels were measured at intervals of irradiation for tensile stresses varying between 100 and 130 MPa and or temperatures between 350 and 4200C. Deuteron irradiation creep of 0.13 mm thick and 20% cold-worked 316 stainless steel alloys was investigated for an irradiation temperature of 3000C by means of a torsional creep facility installed at the Ispra Cyclotron. It was found that the creep rate increases linearly with the displacement rate in the range between 10-6 to 10-5 dpa.s-1. The stress dependence of the irradiation creep rate is quadratic for stresses between 50 and 100 MPa and linear for stresses ranging between 100 and 150 MPa. (author)
Additional details
Publishing Information
- Publisher
- Pergamon Press.
- Imprint Place
- Oxford (UK)
- ISBN
- 0 08 034935 8
- Imprint Title
- Fusion technology 1986. 2 v.
- Imprint Pagination
- 1895 p.
- Journal Page Range
- v. 2. p. 1095-1101.
Conference
- Title
- 14. Symposium on fusion technology.
- Dates
- 8-12 Sep 1986.
- Place
- Avignon (France).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 19025186
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; FIRST WALL; HFR REACTOR; MATERIALS TESTING; PHYSICAL RADIATION EFFECTS; STAINLESS STEELS; TENSILE PROPERTIES; THERMONUCLEAR REACTOR MATERIAL
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STEELS; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; THERMONUCLEAR REACTOR WALLS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EUR--10936-EN.