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HANSF 1.3 Users Manual FAI/98-40-R2 Hanford Spent Nuclear Fuel (SNF) Safety Analysis Model [SEC 1 and 2] [electronic resource].

Published
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1999.
Physical Description
479 pages : digital, PDF file
Additional Creators
United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. This manual reflects the HANSF version 1.3.2, a revised version of 1.3.1. HANSF 1.3.2 was written to correct minor errors and to allow modeling of condensate flow on the MCO inner surface. HANSF 1.3.2 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under Lahey TI or digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments.
Report Numbers
E 1.99:snf-3650, rev.2
snf-3650, rev.2
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
10/07/1999.
"snf-3650, rev.2"
"ECN-656426"
DUNCAN, D.R.
NHC (US)
ENVIRONMENTAL MANAGEMENT (US)
Type of Report and Period Covered Note
Final; 10/07/1999 - 10/07/1999
Funding Information
AC06-96RL13200
View MARC record | catkey: 14664798