Technical conservatism in the design of a spent fuel repository in a generic bedded salt stratigraphy
Description
This report illustrates an approach to quantitatively document the degree of technical conservatism incorporated into the design of a hypothetical geologic waste isolation system in a generic bedded salt stratigraphy. The report develops performance constraints for the critical barriers within each subsystem and for the system as a whole. The interface between integrity and loss of function is quantitatively defined for each performance constraint. A conservative margin is applied to this interface to arrive at a design basis. The waste isolation system design is then analyzed to ensure that the design bases are met for the effective lifetimes of each barrier. This approach enables the reader to scrutinize both the methodology and the design to determine for himself in the degreeof technical conservatism incorporated into the waste isolation design
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 as DE83011127.
Files
Additional details
Publishing Information
- Imprint Pagination
- 40 p.
- Report number
- DOE/NWTS--147(2)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14780313
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING; S58: GEOSCIENCES;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- AFTER-HEAT; EXPERIMENTAL DATA; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; SALT DEPOSITS; SPATIAL DISTRIBUTION; SPECIFICATIONS; SPENT FUELS; STRATIGRAPHY; TEMPERATURE DISTRIBUTION; THERMOELASTICITY
- Descriptors DEC
- DATA; DISTRIBUTION; ELASTICITY; ENERGY SOURCES; FUELS; GEOLOGIC DEPOSITS; INFORMATION; MANAGEMENT; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUCLEAR FUELS; NUMERICAL DATA; REACTOR MATERIALS; WASTE DISPOSAL; WASTE MANAGEMENT