FRAP-T2: a computer code for the transient analysis of oxide fuel rods
Description
Fuel Rod Analysis Program-Transient (FRAP-T) is a FORTRAN IV computer code which can be used to solve the transient response of a light water reactor fuel rod during accidents, such as a loss-of-coolant accident or a power-cooling-mismatch. The coupled effects of mechanical, thermal, internal gas, and material property response on the behavior of the fuel rod are considered. The cladding deformation model includes elastic-plastic deformation. The transient flow of gas between the plenum and gas gap is modeled. FRAP-T is coupled to a material property subcode, MATPRO, which is used to provide gas, fuel and cladding properties to the FRAP-T computational subcodes. No material properties need to be supplied by the code user. The needed water properties are obtained from the 1967 ASME steam tables, which are linked to the code. Critical heat flux and heat transfer correlations for a wide range of coolant conditions are contained in modular subroutines. FRAP-T is a modular code with each major computational model isolated within the code and coupled to the main code by subroutine calls and data transfer through argument lists. The argument lists are completely defined by comment statements at the beginning of each subroutine. The code is presently programmed and running on the IBM 360/75 and CDC 7600 computers
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A16/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 340 p.
- Report number
- TREE-NUREG--1040
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8328184
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; F CODES; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; POWER-COOLING-MISMATCH ACCIDEN; PWR TYPE REACTORS; REACTOR ACCIDENTS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS