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Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding.

DE2001768617

Publication Date	2000
Personal Author	Chung, H. M.; Strain, R. V.; Billone, M. C.
Page Count	6
Abstract	The morphology, number density, orientation, distribution, and crystallographic aspects of Zr hydrides in Zircaloy fuel cladding play important roles in fuel performance during all phases before and after discharge from the reactor, i.e., during normal operation, transient and accident situations in the reactor, temporary storage in a dry cask, and permanent storage in a waste repository. In the past, partly because of experimental difficulties, hydriding behavior in irradiated fuel cladding has been investigated mostly by optical microscopy (OM). In the present study, fundamental metallurgical and crystallographic characteristics of hydride precipitation and reorientation were investigated on the microscopic level by combined techniques of OM and transmission electron and scanning electron microscopy (TEM and SEM) of spent-fuel claddings discharged from several boiling and pressurized water reactors (BWRS and PWRS). Defueled sections of standard and Zr-lined Zircaloy-2 fuel claddings, irradiated to fluences of =3.3 x 1021 n cm-Q and =9.2 x 1021 n cm-Q (E > 1 MeV), respectively, were obtained from spent fuel rods discharged from two BWRS.
Keywords	Spent fuel elements High-level radioactive wastes Thermodynamics Characteristics Metallurgy Crystallography Reorientation Spent fuel cladding Hydride precipitation
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.; Nuclear Regulatory Commission, Washington, DC. Office of Nuclear
Supplemental Notes	See also DE85701199. Sponsored by Department of Energy, Washington, DC. and Nuclear Regulatory Commission, Washington, DC. Office of Nuclear Regulatory Research.
Document Type	Technical Report
NTIS Issue Number	200122

Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding.

Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding.
DE2001768617

Publication Date	2000
Personal Author	Chung, H. M.; Strain, R. V.; Billone, M. C.
Page Count	6
Abstract	The morphology, number density, orientation, distribution, and crystallographic aspects of Zr hydrides in Zircaloy fuel cladding play important roles in fuel performance during all phases before and after discharge from the reactor, i.e., during normal operation, transient and accident situations in the reactor, temporary storage in a dry cask, and permanent storage in a waste repository. In the past, partly because of experimental difficulties, hydriding behavior in irradiated fuel cladding has been investigated mostly by optical microscopy (OM). In the present study, fundamental metallurgical and crystallographic characteristics of hydride precipitation and reorientation were investigated on the microscopic level by combined techniques of OM and transmission electron and scanning electron microscopy (TEM and SEM) of spent-fuel claddings discharged from several boiling and pressurized water reactors (BWRS and PWRS). Defueled sections of standard and Zr-lined Zircaloy-2 fuel claddings, irradiated to fluences of =3.3 x 1021 n cm-Q and =9.2 x 1021 n cm-Q (E > 1 MeV), respectively, were obtained from spent fuel rods discharged from two BWRS.
Keywords	Spent fuel elements High-level radioactive wastes Thermodynamics Characteristics Metallurgy Crystallography Reorientation Spent fuel cladding Hydride precipitation
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.; Nuclear Regulatory Commission, Washington, DC. Office of Nuclear
Supplemental Notes	See also DE85701199. Sponsored by Department of Energy, Washington, DC. and Nuclear Regulatory Commission, Washington, DC. Office of Nuclear Regulatory Research.
Document Type	Technical Report
NTIS Issue Number	200122