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Title: Study of UO/sub 2/ wafer fuel for very high-power research reactors

Abstract

The Reduced Enrichment Research and Test Reactor Program is aimed at reducing fuel enrichment to < 20% in those research and test reactors presently using highly enriched uranium fuel. UO/sub 2/ caramel fuel is one of the most promising new types of reduced-enrichment fuel for use in research reactors with very high power density. Parametric studies have been carried out to determine the maximum specific power attainable without significant fission-gas release for UO/sub 2/ wafers ranging from 0.75 to 1.50 mm in thickness. The results indicate that (1) all the fuel designs considered in this study are predicted not to fail under full-power operation up to a burnup of 1.09 x 10/sup 21/ fis/cm/sup 3/; (2) for all fuel designs, failure is predicted at approximately the same fuel centerline temperature for a given burnup; (3) the thinner the wafer, and wider the margin for fuel specific power between normal operation and increased-power operation leading to fuel failure; (4) increasing the coolant pressure in the reactor core could improve fuel performance by maintaining the fuel at a higher power level without failure for a given burnup; and (5) for a given power level, fuel failure will occur earlier at a highermore » cladding surface temperature and/or under power-cycling conditions. 12 figures, 7 tables.« less

Authors:
; ; ;
Publication Date:
Research Org.:
Argonne National Lab., IL (USA)
OSTI Identifier:
6463868
Report Number(s):
ANL/RERTR/TM-2
ON: DE81026501; TRN: 81-013150
DOE Contract Number:
W-31-109-ENG-38
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; OSIRIS REACTOR; NUCLEAR FUELS; RESEARCH REACTORS; URANIUM DIOXIDE; FUEL ELEMENT FAILURE; FUEL PLATES; PERFORMANCE; ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220600* - Nuclear Reactor Technology- Research, Test & Experimental Reactors; 050700 - Nuclear Fuels- Fuels Production & Properties

Citation Formats

Hsieh, T.C., Jankus, V.Z., Rest, J., and Billone, M.C.. Study of UO/sub 2/ wafer fuel for very high-power research reactors. United States: N. p., 1980. Web. doi:10.2172/6463868.
Hsieh, T.C., Jankus, V.Z., Rest, J., & Billone, M.C.. Study of UO/sub 2/ wafer fuel for very high-power research reactors. United States. doi:10.2172/6463868.
Hsieh, T.C., Jankus, V.Z., Rest, J., and Billone, M.C.. Sat . "Study of UO/sub 2/ wafer fuel for very high-power research reactors". United States. doi:10.2172/6463868. https://www.osti.gov/servlets/purl/6463868.
@article{osti_6463868,
title = {Study of UO/sub 2/ wafer fuel for very high-power research reactors},
author = {Hsieh, T.C. and Jankus, V.Z. and Rest, J. and Billone, M.C.},
abstractNote = {The Reduced Enrichment Research and Test Reactor Program is aimed at reducing fuel enrichment to < 20% in those research and test reactors presently using highly enriched uranium fuel. UO/sub 2/ caramel fuel is one of the most promising new types of reduced-enrichment fuel for use in research reactors with very high power density. Parametric studies have been carried out to determine the maximum specific power attainable without significant fission-gas release for UO/sub 2/ wafers ranging from 0.75 to 1.50 mm in thickness. The results indicate that (1) all the fuel designs considered in this study are predicted not to fail under full-power operation up to a burnup of 1.09 x 10/sup 21/ fis/cm/sup 3/; (2) for all fuel designs, failure is predicted at approximately the same fuel centerline temperature for a given burnup; (3) the thinner the wafer, and wider the margin for fuel specific power between normal operation and increased-power operation leading to fuel failure; (4) increasing the coolant pressure in the reactor core could improve fuel performance by maintaining the fuel at a higher power level without failure for a given burnup; and (5) for a given power level, fuel failure will occur earlier at a higher cladding surface temperature and/or under power-cycling conditions. 12 figures, 7 tables.},
doi = {10.2172/6463868},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Nov 01 00:00:00 EST 1980},
month = {Sat Nov 01 00:00:00 EST 1980}
}

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