Review of Heat Transfer Models in GOTH_SNF for Spent Fuel MCO Calculations
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
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE - EM
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 911529
- Report Number(s):
- DOE/SNF/REP-088; INEEL/MIS-03-01206; TRN: US0704610
- Country of Publication:
- United States
- Language:
- English
Similar Records
Review of Flow Models in GOTH_SNF for Spent Fuel MCO Calculations
Review of Uranium Hydriding and Dehydriding Rate Models in GOTH_SNF for Spent Fuel MCO Calculations
Drop Testing of DOE Spent Nuclear Fuel Canisters
Technical Report
·
Mon Sep 01 00:00:00 EDT 2003
·
OSTI ID:911529
Review of Uranium Hydriding and Dehydriding Rate Models in GOTH_SNF for Spent Fuel MCO Calculations
Technical Report
·
Mon Sep 01 00:00:00 EDT 2003
·
OSTI ID:911529
Drop Testing of DOE Spent Nuclear Fuel Canisters
Conference
·
Fri Jul 01 00:00:00 EDT 2005
·
OSTI ID:911529
+2 more