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

Technical Report · Thu Oct 07 00:00:00 EDT 1999

DOI:https://doi.org/10.2172/798138· OSTI ID:798138

DUNCAN, D R

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.

• Research Organization: NHC (US)
• Sponsoring Organization: ENVIRONMENTAL MANAGEMENT (US)
• DOE Contract Number: AC06-96RL13200
• OSTI ID: 798138
• Report Number(s): SNF-3650, Rev.2; ECN-656426; TRN: US0206097
• Resource Relation: Other Information: PBD: 7 Oct 1999
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CONDENSATES
CONTAINERS
FISSION PRODUCT RELEASE
FORTRAN
HEAT TRANSFER
NUCLEAR FUELS
OXIDATION
PERSONAL COMPUTERS
SAFETY ANALYSIS