The Yucca Mountain Site Characterization Project is evaluating the long-term performance of a high-level nuclear waste form, spent fuel from commercial reactors. Permanent disposal of the spent fuel is possible in a potential repository to be located in the volcanic tuff beds near Yucca Mountain, Nevada. During the post-containment period the spent fuel could be exposed to water condensation since of the cladding is assumed to fail during this time. Spent fuel leach (SFL) tests are designed to simulate and monitor the release of radionuclides from the spent fuel under this condition. This Test Plan addresses the anticipated conditions whereby spent fuel is contacted by small amounts of water that trickle through the spent fuel container. Two complentary test plans are presented, one to examine the reaction of spent fuel and J-13 well water under unsaturated conditions and the second to examine the reaction of unirradiated UO{sub 2} pellets and J-13 well water under unsaturated conditions. The former test plan examines the importance of the water content, the oxygen content as affected by radiolysis, the fuel burnup, fuel surface area, and temperature. The latter test plant examines the effect of the non-presence of Teflon in the test vessel.
[1]
David J. Wronkiewicz,et al.
Repository relevant testing applied to the Yucca Mountain project
,
1990
.
[2]
John K. Bates,et al.
One-year Results of the NNWSI Unsaturated Test Procedure : SRL 165 Glass Application
,
1986
.
[3]
W. J. Gray,et al.
Parametric study of LWR spent fuel dissolution kinetics
,
1992
.
[4]
D. E. Blahnik,et al.
Characterization of spent fuel approved testing material: ATM-106
,
1988
.
[5]
D. E. Blahnik,et al.
Characterization of spent fuel approved testing material: ATM-103
,
1988
.
[6]
A. O. Allen,et al.
Radiation chemistry of aqueous solutions.
,
1948,
The Journal of physical and colloid chemistry.
[7]
P. Cohen.
Water coolant technology of power reactors
,
1980
.