Fission gas retention and axial expansion of irradiated metallic fuel

Conference · Thu May 01 00:00:00 EDT 1986

OSTI ID:7125016

Fenske, G R; Emerson, J E; Savoie, F E; Johanson, E W

Out-of-reactor experiments utilizing direct electrical heating and infrared heating techniques were performed on irradiated metallic fuel. The results indicate accelerated expansion can occur during thermal transients and that the accelerated expansion is driven by retained fission gases. The results also demonstrate gas retention and, hence, expansion behavior is a function of axial position within the pin.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7125016
• Report Number(s): CONF-860931-15; ON: DE87004759
• Resource Relation: Conference: International conference on reliable fuels for liquid metal reactors, Tucson, AZ, USA, 7 Sep 1986; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FISSION PRODUCTS
RETENTION
FUEL PINS
THERMAL EXPANSION
LMFBR TYPE REACTORS
IRRADIATION
PERFORMANCE
SWELLING
TEMPERATURE GRADIENTS
BREEDER REACTORS
EPITHERMAL REACTORS
EXPANSION
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
ISOTOPES
LIQUID METAL COOLED REACTORS
MATERIALS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
210500* - Power Reactors
Breeding