1. NAME AND TITLE
TRIGAP: A Computer Code for TRIGA Type Reactors.
Jozef Stefan Institute, Ljubljana, Yugoslavia through the International Atomic Energy Agency, Vienna and the NEA Data Bank, Gif-sur-Yvette, France
3. CODING LANGUAGE AND COMPUTER
FORTRAN 77; IBM PC.
4. NATURE OF PROBLEM SOLVED
TRIGAP was developed for reactor physics calculations of the 250 kW TRIGA reactor. The program can be used for criticality predictions, power peaking predictions, fuel element burn-up calculations and data logging, and in-core fuel management and fuel utilization improvement.
5. METHOD OF SOLUTION
The program solves the one-dimensional, two-group diffusion equation using the finite- difference method.
6. RESTRICTIONS OR LIMITATIONS
Expected accuracy of the calculations is 1.5% absolute and 0.5% for relative criticality, 15% for power distributions and peakings and 10% for fuel element burnup.
7. TYPICAL RUNNING TIME
The sample problem only took about 1/2 minute on a PC/AT and a few seconds on a PC-486.
8. COMPUTER HARDWARE REQUIREMENTS
TRIGAP runs on the IBM PC with at least 540kb of memory.
9. COMPUTER SOFTWARE REQUIREMENTS
The code was written in FORTRAN 77 and was tested using the Microsoft Version 5.0 compiler.
I. Mele, S. Slavic, and M. Ravink, "Burnup Calculation of TRIGA Fuel Elements - Calculation of Radionuclide Inventories of TRIGA Fuels," IJS-DP-5883 (September 1990).
M. Ravnik, I. Mele, S. Slavic, and B. Zefran, "Development of Computer Programs for Research Reactor Calculations Using Small Computers," IJS-DP-5040 (1987).
I. Mele and M. Ravink, "TRIGAP - A Computer Programme for Research Reactor Calculations IBM.PC. Version," IJS-DP-4238 (December 1985).
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents and a 5.25-in. DS/HD (1.2MB) diskette which includes source codes, sample input and output.
12. DATE OF ABSTRACT
KEYWORDS: BURNUP; CRITICALITY CALCULATIONS;
MICROCOMPUTER; REACTOR PHYSICS