FFTF metal fuel pin sodium bond quality verification

Conference · Thu Dec 01 00:00:00 EST 1988

OSTI ID:6068255

Pitner, A L; Dittmer, J O

The Fast Flux Test Facility (FFTF) Series III driver fuel design consists of U-10Zr fuel slugs contained in a ferritic alloy cladding. A liquid metal, sodium bond between the fuel and cladding is required to prevent unacceptable temperatures during operation. Excessive voiding or porosity in the sodium thermal bond could result in localized fuel melting during irradiation. It is therefore imperative that bond quality be verified during fabrication of these metal fuel pins prior to irradiation. This document discusses this verification.

• Research Organization: Westinghouse Hanford Co., Richland, WA (USA)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 6068255
• Report Number(s): WHC-SA-0455; CONF-890604-5; ON: DE89013506
• Resource Relation: Conference: Annual meeting of the American Nuclear Society, Atlanta, GA, USA, 4 Jun 1989; 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
FFTF REACTOR
FUEL PINS
BONDING
FUEL CANS
SODIUM
VERIFICATION
ALKALI METALS
ELEMENTS
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FUEL ELEMENTS
JOINING
LIQUID METAL COOLED REACTORS
METALS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
210500* - Power Reactors
Breeding