Thermal bonding of light water reactor fuel using nonalkaline liquid-metal alloy

Nuclear Technology

Volumn 115, Issue 3, 1996, Pages 281-291

  Wright, Richard F ^a,c,d,e   Tulenko, James S ^a,f,g,h,i,j   Schoessow, Glen J ^a   Connell Jr , Richard G ^b   Dubecky, Mark A ^b   Adams, Thad ^b  

^a UNIVERSITY OF FLORIDA   (United States)

^b University of Florida   (United States)

^c PENNSYLVANIA STATE UNIVERSITY   (United States)

^d UNIVERSITY OF CALIFORNIA   (United States)

^e Westinghouse Electric Corporation

^f HARVARD COLLEGE   (United States)

^g HARVARD UNIVERSITY   (United States)

^h MASSACHUSETTS INSTITUTE OF TECHNOLOGY   (United States)

ⁱ GEORGE WASHINGTON UNIVERSITY   (United States)

^j BABCOCK AND WILCOX COMPANY   (United States)

more..

Author keywords

Liquid metal bond; Nuclear fuel design; Nuclear fuel temperature

Indexed keywords

COMPUTER SIMULATION; LIGHT WATER REACTORS; LIQUID METALS; MATERIALS TESTING; NUCLEAR FUEL CLADDING; NUCLEAR FUEL PELLETS; PERFORMANCE; THERMAL CONDUCTIVITY; THERMAL EXPANSION; URANIUM COMPOUNDS; ZIRCONIUM ALLOYS;

LIQUID METAL BOND; MATERIALS COMPATIBILITY TESTING; NUCLEAR FUEL DESIGN; NUCLEAR FUEL TEMPERATURE; THERMAL BONDING; URANIUM OXIDES;

NUCLEAR FUELS;

EID: 0030244231     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/nt96-a15838     Document Type: Article

References (12)

1. A. BADRUZZAMAN, "Economic Implications of Annular Fuel in PWRs," Trans. Am. Nucl. Soc., 34, 384 (1980).
2. C. M. MILDRUM and W. B. HENDERSON, "Evaluation of Annular Fuel Economic Benefits for PWRs," Trans. Am. Nucl. Soc., 33, 806 (1979).
3. R. MACDONALD and J. HASTINGS, "Graphite Disc-Oxide Fuel Elements for High Power and Extended Burnup," Proc. Int. Atomic Energy Working Group Water Reactor Fuel Performance Technology, December 1981, p. 110.
4. D. H. GURINSKY and G. J. DIENES, Nuclear Fuels, D. Van Nostrand Company, Princeton, New Jersey (1963).
5. J. A. L. ROBERTSON, Irradiation Effects in Nuclear Fuels, Gordon and Breach, New York (1965).
6. "The University of Chicago Special Committee for the Integral Fast Reactor, Technical Subcommittee Review of Fuel Performance," Argonne National Laboratory-West (July 8, 1987).
7. T. M. ADAMS, "Feasibility Study of Materials Compatibility for Liquid Metal Bonded Light Water Reactor Fuel Elements," Master's Thesis, University of Florida-Gainesville (1993).
8. 2 Compatibility in Liquid Metal Bonded Light Water Reactor Fuel Elements," Master's Thesis, University of Florida-Gainesville (1995).
9. R. F. WRIGHT, "Liquid Bonded Light Water Reactor Fuel: Enhanced Light Water Reactor Safety and Performance," Doctoral Dissertation, University of Florida-Gainesville (1994).
10. A. L. EDWARDS, "TRUMP: A Computer Program for Transient and Steady-State Temperature Distributions in Multidimensional Systems," UCRL-14754, Rev. 3, Lawrence Livermore National Laboratory (Sep. 1, 1972).
11. G. VESTERLUND and L.V. CORSETTI, "Recent ABB Fuel Design and Performance Experience," Proc. Int. Topl. Mtg. Light Water Reactor Fuel Performance, West Palm Beach, Florida, April 17-21, 1994, p. 62, American Nuclear Society (1994).
12. "ESCORE - The EPRI Steady-State Core Reload Evaluator Code: General Description," EPRI NP-5100, Combustion Engineering (Feb. 1987).