1. NAME AND TITLE
INDRA: A Modular System for Calculating the Neutronics and Photonics Characteristics of a
Fusion Reactor Blanket.
DLC-2: Neutron Cross Section Data.
DLC-7: Evaluated Photon Interaction Library
DLC-12: POPLIB-Secondary Gamma-Ray Yield and Cross Section Data.
ENDF/B: Evaluated Nuclear Data File.
The INDRA system was contributed several years ago (1977) and has not been currently updated.
More recent data in each of the above categories is available in RSIC. To use them will necessarily
require changes to the code system.
Max Planck Institute for Plasmaphysik, Federal Republic of Germany.
3. CODING LANGUAGE AND COMPUTER
FORTRAN IV; IBM 360/370.
4. NATURE OF PROBLEM SOLVED
INDRA is a program system allowing a complete evaluation of the neutronics and photonics
characteristics of fusion reactor blankets including neutron and gamma-ray heating rates, tritium
breeding and other reaction rates of interest.
5. METHOD OF SOLUTION
Uncoupled calculation of neutron and gamma-ray transport by well-established discrete ordinates
codes. Preparation of reaction cross-sections by proven computer codes. Auxiliary programs for
evaluating and managing the final results. Data transfer between program modules mostly by magnetic
6. RESTRICTIONS OR LIMITATIONS
This version of INDRA permits only one-dimensional calculations to be performed. Further
restrictions are set by data availability.
7. TYPICAL RUNNING TIME
Running time depends heavily on the size of the problem. It is different for the single modules.
For the sample problems, the following running times were needed: SUPERTOG-332 sec; MACK2
min; GROUCO1 sec; APRFX32 sec; TREVED1 min; DRP2 sec; TAPEMAKER2 sec; DTFMF2
sec; DTF-IV4 sec; ANISN4 sec; CROSS1 sec; POPMAKER1 sec; POPOP41.5 sec; MUG1 min;
GAMSO1 sec; GLUCKE1 sec; FLUZI5 sec; GLOUMAN3 sec.
8. COMPUTER HARDWARE REQUIREMENTS
The code was designed to run on the IBM 360/370 Operating System.
9. COMPUTER SOFTWARE REQUIREMENTS
A FORTRAN IV compiler is required.
R. T. Perry, H. Gorenflo, and W. Danner, "INDRA: A Program System for Calculating the
Neutronics and Photonics Characteristics of a Fusion Reactor Blanket," IPP 4/137 (January 1976).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one tape cartridge in TAR format which contains the
source codes and sample problem input and output.
12. DATE OF ABSTRACT
KEYWORDS: NEUTRON; GAMMA-RAY; DISCRETE ORDINATES; ONE-DIMENSION; MULTIGROUP; CROSS SECTION PROCESSING