Effects of boiling water reactor irradiation on tensile properties of Zircaloy

Published 1974 | Version v1

Report Metadata-only

1. General Electric Co., San Jose, Calif. (USA). Boiling Water Reactor Systems Dept.
2. General Electric Co., Pleasanton, Calif. (USA). BWR Systems Dept.
3. Institutt for Atomenergi, Kjeller (Norway)

no abstract available

Availability note (English)

Available from GfK.

Imprint Title: European conference on irradiation behaviour of fuel cladding and core component materials
Imprint Pagination: p. 189-192.
Report number: AED-Conf--74-587-000

Title: European conference on irradiation behaviour of fuel cladding and core component materials.
Dates: 3 Dec 1974.
Place: Karlsruhe, F.R. Germany.

Country of Publication: Germany
Country of Input or Organization: Germany
INIS RN: 6192144
Subject category: S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator: Conference, No Abstract, Non-conventional Literature
Descriptors DEI: BWR TYPE REACTORS; CHANNELING; DEFORMATION; DISLOCATIONS; DUCTILITY; ELECTRON MICROSCOPY; ELONGATION; FAST NEUTRONS; FRACTURES; HELIUM; HIGH TEMPERATURE; MECHANICAL TESTS; MEDIUM TEMPERATURE; MICROSTRUCTURE; NEUTRON FLUENCE; OXYGEN; PHYSICAL RADIATION EFFECTS; QUANTITY RATIO; QUENCHING; SAMPLE PREPARATION; STRAINS; STRESSES; TENSILE PROPERTIES; TEXTURE; WATER; WELDED JOINTS; YIELD STRENGTH; ZIRCALOY 2; ZIRCALOY 4
Descriptors DEC: ALLOYS; BARYONS; CHROMIUM ADDITIONS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELEMENTARY PARTICLES; ELEMENTS; FAILURES; FERMIONS; HADRONS; HEAT TREATMENTS; HYDROGEN COMPOUNDS; IRON ADDITIONS; JOINTS; LINE DEFECTS; MATERIALS TESTING; MECHANICAL PROPERTIES; MICROSCOPY; NEUTRONS; NONMETALS; NUCLEONS; OXYGEN COMPOUNDS; RADIATION EFFECTS; RARE GASES; REACTORS; TESTING; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Notes: 8 figs.; 1 tab.; 4 refs. Short communication only. Imprint:Available from GfK.
Secondary number(s): AED-Conf--74-587-046.