Pressurized water reactor lateral core response routine, FAMREC (Fuel Assembly Mechanical Response Code)
Description
The nonlinear lateral mechanical response of pressurized water reactor fuel assemblies is defined by a computer code, Fuel Assembly Mechanical Response Code (FAMREC), which was generated from a series of existing subcodes. The basic subcodes used were taken directly from the FORTRAN Matrix Analysis (FORMA) library developed at the Martin Marietta Corporation, Denver Division. Several additional subcodes were incorporated into this library to allow for various methods of calculating fuel assembly impact forces and spacer grid crushing loads. A description, including some basic modeling assumptions, is presented for the class of problems which may be solved by the code. The various methods used for calculating fuel assembly impact forces and spacer grid crushing loads are outlined and a short discussion concerned with the overall convergence of the code is included. Results obtained from previous analyses using the code are considered and conclusions concerning the usefulness of these results are presented
Availability note (English)
MF available from INIS under the Report Number; NTI.
Files
Additional details
Publishing Information
- Imprint Pagination
- 183 p.
- Report number
- NUREG/CR--1019
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11522882
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; DEFORMATION; F CODES; FUEL ASSEMBLIES; IMPACT SHOCK; IMPACT STRENGTH; PWR TYPE REACTORS; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- MECHANICAL PROPERTIES; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS