1. NAME AND TITLE
STACY: Source Term Analysis Code
System.
2. CONTRIBUTORS
Contributed
by: International Atomic Energy Agency, Through the OECD Nuclear Energy Agency
Data Bank, Issy-Les Moulineaux, France.
Developed
by: Institute for Reactor Safety and Reactor Technology RWTH-Aachen, Germany.
3. CODING LANGUAGE AND COMPUTER
No specified programming language, Windows, Linux (C859PCX8600).
4. NATURE OF PROBLEM SOLVED
Source Term
Analysis Code System (or STACY) is a tool to predict the fission product
release from spherical fuel elements and the TRISO fuel performance under given
normal or accidental conditions. Developed from older codes – FRESCO-I,
FRESCO-II, PANAMA and SPATRA – the STACY package was modernized in FORTRAN
95/2003 to enable more detailed analysis, including source term estimation,
coated particle failure rate, distinct pebble radius temperature profile etc.
Additional STACY capabilities allow for the simulation of the redistribution of
fission products within the primary circuit and the deposition of fission
products on graphitic and metallic surfaces. STACY will later become a module
within the V/HTR Code Package (HCP).
5. RESTRICTIONS OR LIMITATIONS
None noted.
6. TYPICAL RUNNING TIME
Dependent on input file parameters. Typical problems can run
in less than five minutes.
7. COMPUTER HARDWARE
REQUIREMENTS
Windows, Linux
8. COMPUTER SOFTWARE REQUIREMENTS
Fortran 95/2003.
9. REFERENCES
Contributed
by:
International
Atomic Energy Agency
Wagrammer
Strasse 5, 1210 Vienna, Austria
Developed
by:
Forschungszentrum
Jülich
52425
Jülich, Germany
Institute
for Reactor Safety and Reactor Technology RWTH-Aachen
52064
Aachen, Germany
10. CONTENTS OF CODE PACKAGE
The package was transmitted
digitally as a download link in .zip format. It includes reference material,
documentation, and sample problems.
11. DATE OF ABSTRACT
December 2022
KEYWORDS: fission
gas release, fission products, high temperature reactors.