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Title: IRRADIATION OF U-Mg MATRIX FUEL MATERIAL TO HIGH EXPOSURES

Abstract

An experiment designed to evaluate the in-pile performamce of the U--Mg fuel material when irradiated to high burnups was completed. Twelve specimens of the fuel material which contained uranium particles that packed 5O volume% uranium in a magnesium matrix were canned in Zircaloy cans and irradiated to 0.1, 0.5, 1.0, and 2.0% burnup of the total uranium atoms. Six of the samples contained a matrix of pure magnesium and 6 contained a matrix of Mg--4 wt.% Si in order to compare the effects of irradiation. Load-deflection curves for the irradiated specimens showed that the material lost most of its ductility as a result of the neutron flux and that the maximum load required for failure increased. Most of the damage caused by ir- . radiation became saturated at relatively low burnups. The results of the bond tests showed a slight decrease in the ultimate strength of the material as the exposure was increased. However, the maximum deflections at failure did not change with exposure. The samples containing an alloy matrix of Mg--0.4 wt.% Si had better boiling water corrosion resistance than samples containing a pure magnesium matrix. The irradiated samples containing an alloy matrix decanned easier thsn the others. Thismore » material was found to be capable of withstanding high specific power generation, was dimensionally stable, relatively resistant to radiation damage and apparently had satisfactory fission product retention properties. (M.C.G.)« less

Authors:
;
Publication Date:
Research Org.:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
OSTI Identifier:
4022549
Report Number(s):
HW-43973(Del.)
NSA Number:
NSA-15-017368
DOE Contract Number:  
W-31-109-ENG-52
Resource Type:
Technical Report
Resource Relation:
Other Information: Declassified with deletions Feb. 19, 1960. Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; ADSORPTION; BOILING; BURNUP; CORROSION; DISPERSIONS; DUCTILITY; FAILURES; FISSION PRODUCTS; FUEL CANS; FUELS; IRRADIATION; MAGNESIUM; MAGNESIUM ALLOYS; MATERIALS TESTING; NEUTRON FLUX; PARTICLES; RADIATION EFFECTS; REACTORS; SEPARATION PROCESSES; SILICIDES; STABILITY; TENSILE PROPERTIES; URANIUM; WATER; ZIRCALOY

Citation Formats

Freshley, M.D., and Last, G.A. IRRADIATION OF U-Mg MATRIX FUEL MATERIAL TO HIGH EXPOSURES. United States: N. p., 1956. Web.
Freshley, M.D., & Last, G.A. IRRADIATION OF U-Mg MATRIX FUEL MATERIAL TO HIGH EXPOSURES. United States.
Freshley, M.D., and Last, G.A. Wed . "IRRADIATION OF U-Mg MATRIX FUEL MATERIAL TO HIGH EXPOSURES". United States.
@article{osti_4022549,
title = {IRRADIATION OF U-Mg MATRIX FUEL MATERIAL TO HIGH EXPOSURES},
author = {Freshley, M.D. and Last, G.A.},
abstractNote = {An experiment designed to evaluate the in-pile performamce of the U--Mg fuel material when irradiated to high burnups was completed. Twelve specimens of the fuel material which contained uranium particles that packed 5O volume% uranium in a magnesium matrix were canned in Zircaloy cans and irradiated to 0.1, 0.5, 1.0, and 2.0% burnup of the total uranium atoms. Six of the samples contained a matrix of pure magnesium and 6 contained a matrix of Mg--4 wt.% Si in order to compare the effects of irradiation. Load-deflection curves for the irradiated specimens showed that the material lost most of its ductility as a result of the neutron flux and that the maximum load required for failure increased. Most of the damage caused by ir- . radiation became saturated at relatively low burnups. The results of the bond tests showed a slight decrease in the ultimate strength of the material as the exposure was increased. However, the maximum deflections at failure did not change with exposure. The samples containing an alloy matrix of Mg--0.4 wt.% Si had better boiling water corrosion resistance than samples containing a pure magnesium matrix. The irradiated samples containing an alloy matrix decanned easier thsn the others. This material was found to be capable of withstanding high specific power generation, was dimensionally stable, relatively resistant to radiation damage and apparently had satisfactory fission product retention properties. (M.C.G.)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1956},
month = {8}
}

Technical Report:
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