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Data report on leach tests of Pu-doped UO/sub 2/ in PBB1 brine: Salt Repository Project

Technical Report ·
OSTI ID:6051228
This report provides results from a series of leach tests conducted using nonirradiated uranium dioxide (UO/sub 2/) doped with plutonium (Pu) to simulate the alpha activity of spent fuel specimens used in recent spent fuel leach tests. The purpose was to determine whether alpha radiation from the spent fuel could be responsible for uranium release values in spent fuel leach tests in salt brine that were at least 100 times greater than from similar tests with nonirradiated UO/sub 2/ pellets. The data in this data report are preliminary; they have been neither analyzed nor evaluated. 2 refs., 2 figs., 8 tabs.
Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
6051228
Report Number(s):
PNL/SRP-6284; ON: DE88002091
Country of Publication:
United States
Language:
English