Published 1990 | Version v1
Miscellaneous

Postirradiation examination of steels and alloys irradiated up to high damageing doses

  • 1. Vsesoyuznyj Nauchno-Issledovatel'skij Inst. Neorganicheskikh Materialov, Moscow (USSR)
  • 2. Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)

Description

Presented are the results from the examinations of fuel cans made of austenitic, ferritic-martensite steels and high nickel alloys irradiated within the temperature range of 350-700 deg C to the damage doses of 78-86 dpa in BOR-60 and BN-600 reactors. The dose and temperature relations of mechanical properties and material swelling are obtained. The change of properties of material studied is analysed with accounting for structure, composition and irradiation conditions. 5 refs.; 14 figs.; 3 tabs

Additional details

Additional titles

Original title (Russian)
Результаты послереакторных исследований сталей и сплавов, облученных до высоких повреждающих доз

Publishing Information

Imprint Title
Radiation materials science. V. 3
Imprint Pagination
224 p.
Journal Page Range
p. 96-109.
Report number
INIS-SU--271

Conference

Title
International conference on radiation materials science.
Dates
22-25 May 1990.
Place
Alushta (USSR).

Optional Information

Notes
Imprint:Radiatsionnoe materialovedenie. Tom 3.