Metallic fuel safety assessment

Technical Report · Wed Feb 01 00:00:00 EST 1989

DOI:https://doi.org/10.2172/10200877· OSTI ID:10200877

Bauer, T. H.; Cahalan, J. E.; Dunn, F. E.; Fenske, G. R.; Gabor, J. D.; Gruber, E. E.; Hughes, T. H.; Kalimullah, none; Kramer, J. M.; Miles, K. J.; Pedersen, D. R.; Spencer, B. W.; Tentner, A. M.; Tilbrook, R. W.; Wright, A. E.

A survey of experimental and analytical results from the Integral Fast Reactor (IFR) safety program are presented, with a focus on metallic fuel safety performance. Experimental results from laboratory and in-pile tests are reviewed. Models of metallic fuel behavior for prediction of performance in reactor transients and accidents are summarized. Analyses of metallic fuel response in design basis accidents and anticipated transients without scram are presented. The experimental and analytical databases demonstrate the superior safety performance of metallic fuel in IFR design concepts.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10200877
• Report Number(s): ANL-IFR-102; ON: TI96020188
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
IFR REACTOR
FUEL ELEMENTS
REACTOR SAFETY
RESEARCH PROGRAMS
PERFORMANCE
TESTING
DESIGN BASIS ACCIDENTS
ATWS
FUEL CANS
HEAT TRANSFER
HYDRAULICS
TREAT REACTOR
F CODES
S CODES
FAILURES
BONDING
LOSS OF FLOW
FFTF REACTOR
PIPES
RUPTURES
LOSS OF COOLANT
220900
210500
220300
POWER REACTORS
BREEDING