Analysis of radiation embrittlement results from a French forging examined in the second phase of an IAEA-coordinated research program
- 1. Commissariat a l'Energie Atomique, Gif-sur-Yvette (France). Centre d'Etudes Nucleaires de Saclay
- 2. Framatome, Fiat (France). Materials and Technology Dept.
- 3. Creusot-Loire Industrie, Creusot (France). Centre de Recherches des Materiaux du Creusot (France)
- 4. DER-Les Renardieres, Moret-sur-Loing (France). Electricite de France
Description
Test blocks of a manganese-nickel-molybdenum (Mn-Ni-Mo) low-alloy steel, machined from a nozzle cut-out of a 230-mm-thick forging shell, were provided by France in 1978 to be investigated in the second phase of an IAEA-coordinated research program on the behavior of advanced pressure vessel steels under neutron irradiation. The results obtained by different laboratories exhibit a great deal of scattering in Charpy-5 transition temperatures, both in the initial condition and after neutron irradiation. Therefore, the shifts in Charpy-5 transition curves induced by neutron irradiation at similar fluences of about 3 x 1023 n · m-2 (E ≥ 1 MeV) cover a wide temperature range from 0 up to 110 C. A more detailed investigation of these results was undertaken, and additional Charpy tests were conducted to clarify the considerable uncertainty about the sensitivity of this forging to radiation embrittlement. The differences in results were found to be due to the various orientations and locations of the Charpy-5 specimens extracted by the different laboratories, in some cases to insufficient test data in the transition region of the Charpy curve, and to the detrimental effect on Charpy-5 properties of segregated zones (ghost lines) found in specific locations of large forgings
Additional details
Publishing Information
- Publisher
- American Society for Testing and Materials.
- Imprint Place
- Philadelphia, PA (United States)
- ISBN
- 0-8031-1478-8
- Imprint Title
- Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (Fourth Volume)
- Imprint Pagination
- 414 p.
- Journal Page Range
- p. 249-265.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25021228
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COORDINATED RESEARCH PROGRAMS; EMBRITTLEMENT; EXPERIMENTAL DATA; FORGING; IAEA; IMPACT TESTS; LOW ALLOY STEELS; NEUTRONS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; SEGREGATION
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CONTAINERS; DATA; ELEMENTARY PARTICLES; FABRICATION; FERMIONS; HADRONS; INFORMATION; INTERNATIONAL ORGANIZATIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MATERIALS WORKING; MECHANICAL TESTS; NUCLEONS; NUMERICAL DATA; RADIATION EFFECTS; RESEARCH PROGRAMS; STEELS; TESTING