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RSIC CODE PACKAGE CCC-410


1. NAME AND TITLE

THIDA-2: Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors.

AUXILIARY ROUTINES

GXC: BCD to Binary Converter GICX40 Data Library.

ACT4: Induced Activity Gamma-Ray Source Calculation.

ANISN: One-Dimensional Discrete Ordinates Transport Calculation.

APPLE-2: Gamma-Ray Flux to Shutdown Dose Rate Converter and Plotter.

MIXE: Mixture-Editing Code.

DOT3.5: Two-Dimensional Discrete Ordinates Transport Calculation.

MORSE-GG: Three-Dimensional Monte Carlo Calculation.

TOPIC: Geometry Preparation and Visualization.

DATA LIBRARIES

CHAINLIB: Transmutation and Decay Chain Data Library.

CROSSLIB: 42 Group Transmutation Cross-Section Data Library.

GAMMALIB: Delayed Gamma-Ray Emission Data Library.

GICX40: 42 Group Neutron Cross-Section Library.

GROUPIN: 54 Group Gamma-Ray Cross-Section Library.

GFLXDOSE: Gamma Ray Flux-to-Dose Rate Conversion Factor Data.

2. CONTRIBUTOR

Japan Atomic Energy Research Institute (JAERI), Tokai-Mura, Ibaraki-Ken, Japan.

3. CODING LANGUAGE AND COMPUTER

Fortran 77; IBM 360. (C00410FM38000)

4. NATURE OF PROBLEM SOLVED

THIDA-2 calculates transmutation, radioactivity, decay heat and dose rate for a fusion reactor using one-, two-, and three-dimensional geometrical models.

5. METHOD OF SOLUTION

The neutron flux in and around an operating fusion device is calculated using ANISN, DOT-3.5, or MORSE-GG. The neutron flux is used as input to ACT4 which calculates the induced activity, the approximate decay heat and the delayed gamma-ray source after a pulsed operation. The Matrix Exponential Method is used to solve the decay chain equations to obtain time-dependent nuclide densities. The delayed gamma-ray source serves as input for the transport calculation of the delayed gamma-ray flux during shutdown, using the same transport code as was used for the neutron flux calculation. The gamma-ray flux is converted to shutdown dose rate and the decay heat is calculated and these quantities are plotted by the APPLE-2 code.



6. RESTRICTIONS OR LIMITATIONS

Sequential decay of two short-lived nuclides cannot be calculated accurately, reactions of neutrons with reaction products are not considered, and neutron flux change caused by transmutation cannot be treated in a single calculation.

7. TYPICAL RUNNING TIME

Problem dependent, with times ranging from 80s to 20m for an iron cylinder problem run in one dimension and three dimensions, respectively, on an IBM 360.

8. COMPUTER HARDWARE REQUIREMENTS

THIDA is operable on the IBM 360 and numerous scratch and permanent storage devices are required.

9. COMPUTER SOFTWARE REQUIREMENTS

A Fortran 77 compiler is required.

10. REFERENCE

Y. Seki, H. Iida, H. Kawasaki and K. Yamada, "THIDA-2: An Advanced Code System for Calculation of Transmutation, Activation, Decay Heat and Dose Rate," JAERI 1301 (March 1986).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and three DS/HD 3.5-in. (1.44 MB) diskettes in self-extracting compressed DOS files which contain the source codes, data libraries, sample problem input and output.

12. DATE OF ABSTRACT

February 1982; revised February 1983; March 1984; April 1987.

KEYWORDS: NEUTRON; GAMMA-RAY SOURCE; ONE-DIMENSION; DISCRETE ORDINATES; TWO-DIMENSIONS; ACTIVATION; ISOTOPE INVENTORY; MULTIGROUP; CTR; MONTE CARLO; COMPLEX GEOMETRY