Fission gas retention in irradiated metallic fuel

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:6303957

Fenske, G R; Gruber, E E; Kramer, J M

Theoretical calculations and experimental measurements of the quantity of retained fission gas in irradiated metallic fuel (U-5Fs) are presented. The calculations utilize the Booth method to model the steady-state release of gases from fuel grains and a simplified grain-boundary gas model to predict the gas release from intergranular regions. The quantity of gas retained in as-irradiated fuel was determined by collecting the gases released from short segments of EBR-II driver fuel that were melted in a gas-tight furnace. Comparison of the calculations to the measurements shows quantitative agreement with both the magnitude and the axial variation of the retained gas content.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6303957
• Report Number(s): CONF-870812-23; ON: DE87011462; TRN: 87-030043
• Resource Relation: Conference: 9. SMIRT: international conference on structural mechanics in reactor technology, Lausanne, Switzerland, 17 Aug 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
FUEL PINS
FISSION PRODUCT RELEASE
PHYSICAL RADIATION EFFECTS
EBR-2 REACTOR
EXPERIMENTAL DATA
FISSION PRODUCTS
GASES
IRRADIATION
STEADY-STATE CONDITIONS
THEORETICAL DATA
TRANSIENTS
BREEDER REACTORS
DATA
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUIDS
FUEL ELEMENTS
INFORMATION
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NUMERICAL DATA
POWER REACTORS
RADIATION EFFECTS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
220300* - Nuclear Reactor Technology- Fuel Elements