Research within the coordinated programme on irradiation embrittlement of pressure vessel steels
Creators
- 1. Gesellschaft fuer Kernenergieverwertung in Schiffbau und Schiffahrt m.b.H., Geesthacht-Tesperhude (F.R. Germany)
Description
Samples of the pressure vessel steel ASTM A533 Grade B Class 1 will be irradiated and different materials tests are to be carried out. Charpy V-notch specimens, 48 tensile and 10 WOL-1X specimens will be neutron-irradiated in several capsules in the Material Test Reactor FRG-2 in Geesthacht. The irradiation temperature is 100degC and 290degC respectively. The neutron doses are 5x1018, 2x1019 and 1x1020 n/cm2 (Esub(n)>1 MeV). The fluence is measured with several neutron monitors (Co, Ag, In, Ni etc.). After the irradiation, the following tests will be done in the hot cell facilities: Impact test at the whole transition region and determination of the transition temperature, tensile test (tensile strength, yield strength, elongation, reduction of area), hardness test, Ksub(IC) test
Additional details
Publishing Information
- Imprint Title
- Co-ordinated research programme on irradiation embrittlement of pressure vessel steels
- Imprint Pagination
- p. 85-94.
- Report number
- IAEA--176
Conference
- Title
- Research co-ordination meeting on irradiation embrittlement of reactor pressure vessel steels.
- Dates
- 23 Oct 1974.
- Place
- Vienna, Austria.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 7237482
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COORDINATED RESEARCH PROGRAMS; EMBRITTLEMENT; IRRADIATION; IRRADIATION CAPSULES; PRESSURE VESSELS; STEEL-ASTM-A533-B
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CARBON STEELS; CONTAINERS; IRON ALLOYS; IRON BASE ALLOYS; RESEARCH PROGRAMS; STEELS; TRANSITION ELEMENT ALLOYS