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

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)