Effect of High Temperature In-pile Irradiation Upon High Density UO2 Bodies PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
As a part of the ML-1 fuel evaluation program, high density bulk UO2 pellets were irradiated to burnups equivalent to 8500 hours of ML-1 reactor operation (3.0 a/o U-235) under temperature conditions approximating those expected in the reactor (1750°F peak cladding surface temperature). Post irradiation examination revealed severe fuel cracking although fission product gas release measurements agreed well with calculated values. No structural changes were revealed by metallography and X-ray diffraction except for a small unidentified phase observed at the fuel grain boundaries. This phase is considered to be the result of impurities or fission product gas sites. The data obtained on UO2 fuel is in agreement with that determined in irradiation experiments performed at other facilities. The performance of UO2 fuel was sufficiently good to permit use in the ML-1 reactor.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
As a part of the ML-1 fuel evaluation program, high density bulk UO2 pellets were irradiated to burnups equivalent to 8500 hours of ML-1 reactor operation (3.0 a/o U-235) under temperature conditions approximating those expected in the reactor (1750°F peak cladding surface temperature). Post irradiation examination revealed severe fuel cracking although fission product gas release measurements agreed well with calculated values. No structural changes were revealed by metallography and X-ray diffraction except for a small unidentified phase observed at the fuel grain boundaries. This phase is considered to be the result of impurities or fission product gas sites. The data obtained on UO2 fuel is in agreement with that determined in irradiation experiments performed at other facilities. The performance of UO2 fuel was sufficiently good to permit use in the ML-1 reactor.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
As a part of the ML-1 reactor fuel evaluation program, UO2-- BeO bodies containing two UO2 compositions, 70 and 80 wt% UO2, were irradiated to a burnup equivalent to 8750 hours of ML-1 reactor operation (8.5% U/ sup 235/). It was estimated that maximum cladding surface temperatures of 1710 nif- F were attained during irradiation. Reference design burnup for the ML-1 is 9.7% U235, in 10,000 hours of operation at maximum clad surface temperatures of 1750 nif- F. Postirradiation examination of the test specimens revealed that the cladding of one of the 80 wt% UO2-- BeO specimens had ruptured after severe swelling. All other specimens showed little external effect from the irradiation. Fission gas release from the fuel varied between 0.59 and 2.7% except for the failed specimen which released about 69%. Considerable change was observed in the microstructure of the irradiated specimens although subsequent x-ray diffraction examination did not indicate serious damage to the crystal structure of either the BeO or UO2. The data obtained from this experiment are in substantial agreement with that determined in irradiation experiments performed at other facilities. The performance of 70 wt% UO2--BeO was considered to be suitable for use in the ML-1 reactor. (auth).
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Author: G. W. Titus
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Author: John D. Eichenberg
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Author: U.S. Atomic Energy Commission
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Author: U.S. Atomic Energy Commission
Author: American Ceramic Society