Irradiation embrittlement of reactor pressure vessel steels (Report on analysis of the behaviour of advanced reactor pressure vessel steel under neutron irradiation)
Creators
- 1. Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.
Description
The International Working Group on Reliability of Reactor Pressure Components (IWG-RRPC) sponsored by IAEA launched a Coordinated Research Programme in 1977 to investigate the behaviour of Advanced Pressure Vessel Steels under neutron irradiation. IWG-RRPC included provision of various materials produced by organisation in Federal Republic of Germany, France, Japan and a reference Steel from United States of America to those countries participating in the programme. India joined the International Programme in 1977. The scope of study was mainly to evaluate the neutron irradiation induced change in nil ductility transition temperature and tensile properties on some selected materials. The required quantity of these materials was received from Japan, France, Federal Republic of Germany and United States of America. The paper reports the results obtained from the investigations carried out in the Radiometallurgy Division of Bhabha Atomic Research Centre, Trombay, Bombay, India, on Japanese plate, Japanese forging, French plate, French forging and French weld. Due to other important commitments of the CIRUS reactor, in which the irradiation was carried out, it was not possible to complete the entire programme at this time. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
16068218.pdf
Files
(2.0 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 60 p.
- Report number
- BARC--1237
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 16068218
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- EMBRITTLEMENT; FAST NEUTRONS; HARDNESS; IMPACT TESTS; IRRADIATION; METALLOGRAPHY; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTOR COMPONENTS; REACTOR MATERIALS; SAMPLE PREPARATION; STEELS; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CONTAINERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; NEUTRONS; NUCLEONS; RADIATION EFFECTS; RADIATION FLUX; TESTING
Optional Information
- Notes
- 25 tabs.; 24 figs.