Published September 1, 2003
| Version v1
Report
Review of Heat Transfer Models in GOTH()SNF for Spent Fuel MCO Calculations
Description
The present report is one of a series of three. The series provides an independent technical review of certain aspects of the GOTH-SNF code that is used for accident analysis of the multicanister overpack that is proposed for permanent storage of spent nuclear fuel in the planned repository at Yucca Mountain, Nevada. The work documented in the present report and its two companions was done under the auspices of the National Spent Nuclear Fuel Program. The other two reports in the series are DOE/SNF/REP-0871 and DOE/SNF/REP-089.2.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- DOE/SNF/REP--088
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 39004880
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ACCIDENTS; HEAT TRANSFER; NUCLEAR FUELS; SPENT FUELS; STORAGE; YUCCA MOUNTAIN
- Descriptors DEC
- ENERGY SOURCES; ENERGY TRANSFER; FUELS; MATERIALS; MOUNTAINS; NUCLEAR FUELS; REACTOR MATERIALS
Optional Information
- Contract/Grant/Project number
- INEEL/MIS-03-01206; AC07-99ID-13727
- Notes
- doi 10.2172/911529
- Funding organization
- DOE - EM (United States)