Published September 1979 | Version v1
Report Restricted

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

Restricted

The record is publicly accessible, but files are restricted to users with access.

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