The release of cesium and the actinides from spent fuel under unsaturated conditions
Conference
·
OSTI ID:204650
Tests designed to be similar to the unsaturated and oxidizing conditions expected in the candidate repository at Yucca Mountain are in progress with spent fuel at 90{degree}C. The similarities and the differences in release behavior for {sup 137}Cs during the first 2.6 years and the actinides during the first 1.6 years of testing are presented for tests done with (1) water dripped on the fuel at a rate of 0.075 and 0.75 mL every 3.5 days and (2) in a saturated water vapor environment.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38; W-7405-ENG-48
- OSTI ID:
- 204650
- Report Number(s):
- ANL/CMT/CP--86952; CONF-951155--60; ON: DE96007205
- Country of Publication:
- United States
- Language:
- English
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