Published October 1972 | Version v1
Journal article Metadata-only

Fuel-cladding mechanical interaction in LMFBR fuel rods

Creators

Description

Experimental determinations of cladding plastic deformation in (U,Pu)O2 fuel rods, clad with annealed Type 316 stainless steel and irradiated in EBR-II, indicate that fuel-cladding mechanical interaction takes place between ∼3 and 8 at.% burnup. At higher burnups, the cladding swelling rate increases markedly resulting in no further fuel-induced plastic deformation. The maximum cladding plastic strain exhibited by several annealed Type 316 stainless-steel-clad rods was 0.4%. Cladding plastic strain was found to be independent of smeared density in the range of 83 to 91% TD.

Additional details

Additional titles

Augmented title (English)
316-Stainless clad UO_2--PuO_2

Identifiers

DOI
10.13182/nt72-a31178;

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
16
Journal Issue
1
Series
Nucl. Technol.
Journal Page Range
89-99
ISSN
0029-5450

Conference

Title
Conference on reactor materials performance.
Dates
24 Apr 1972.
Place
Richland, Washington, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
5093938
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BINARY MIXTURES; BURNUP; FBR TYPE REACTORS; FUEL CANS; FUEL RODS; PHYSICAL RADIATION EFFECTS; PLUTONIUM OXIDES; STAINLESS STEEL-316; STRAINS; SWELLING; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ALLOYS; BREEDER REACTORS; CHALCOGENIDES; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; DISPERSIONS; EPITHERMAL REACTORS; FAST REACTORS; FUEL ELEMENTS; IRON ALLOYS; MIXTURES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; STAINLESS STEELS; STEELS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
See CONF-720420--.; Updated automatically by Metadata and Full-Text Enrichment Agent