Potential {sup 14}CO{sub 2} releases from spent fuel containers at Yucca Mountain
The potential release of gaseous {sup 14}CO{sub 2} from small perforations in spent fuel containers has been evaluated as a function of temperature, hole size, effective porosity of corrosion products within the hole, and time, based on the waste package design parameters and environmental conditions described in the Yucca Mountain Site Characterization Report (SCP). The SCP does not specify initial fill gas (argon) pressure and temperature. It is shown that, if significant {sup 14}C oxidation takes place during the initial, inert-gas phase, an incentive exists to initially underpressurize the containers. This will avoid large, spiked releases of gaseous {sup 14}CO{sub 2} and will result in delayed, smaller, and more uniform release rates over time. Therefore larger size perforations could be tolerated while meeting the applicable regulations. 16 refs., 2 figs., 3 tabs.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 138015
- Report Number(s):
- BNL-45658; CONF-910435-49; ON: DE91008091; TRN: 91:005937
- Resource Relation:
- Conference: 2. annual American Nuclear Society (ANS) international high level radioactive waste management conference, Las Vegas, NV (United States), 28 Apr - 3 May 1991; Other Information: PBD: [1991]
- Country of Publication:
- United States
- Language:
- English
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Modeling of gaseous {sup 14}CO{sub 2} release from perforations in spent fuel disposal containers
Modeling of gaseous sup 14 CO sub 2 release from perforations in spent fuel disposal containers
Related Subjects
05 NUCLEAR FUELS
CARBON 14 COMPOUNDS
EMISSION
SPENT FUELS
UNDERGROUND DISPOSAL
SPENT FUEL CASKS
PERFORMANCE TESTING
RELEASE LIMITS
CARBON DIOXIDE
YUCCA MOUNTAIN
GASEOUS WASTES
TEMPERATURE DEPENDENCE
POROSITY
CORROSION
OXIDATION
MATHEMATICAL MODELS
HIGH-LEVEL RADIOACTIVE WASTES
MONITORING
ARGON
Yucca Mountain Project