last modified: 17-MAR-1982 | catalog | categories | new | search |

NEA-0668 TRD-3.

TRD-3, In-Core and Out-Core Neutron Flux, Gamma Flux by 2-D Removal Diffusion in Cylindrical Geometry

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1. NAME OR DESIGNATION OF PROGRAM:  TRD-3.
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2. COMPUTERS
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Program name Package id Status Status date
TRD-3 NEA-0668/01 Tested 17-MAR-1982

Machines used:

Package ID Orig. computer Test computer
NEA-0668/01 IBM 3033 IBM 3033
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3. DESCRIPTION OF PROBLEM OR FUNCTION

Calculation of in-core and out- core neutron and gamma flux distributions, by two-dimensional removal diffusion calculation in cylindrical geometry.
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4. METHOD OF SOLUTION

The removal neutron flux is divided into 18 energy groups. The diffusion neutron flux is divided into 26 energy  groups.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

NEA-DB executed all test cases on IBM 3033 in 85 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-0668/01 17-MAR-1982 Tested at NEADB
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10. REFERENCES

- R.G. Jaeger et al.:
  "Engineering Compendium on Radiation Shielding"
  Vol. I, Spriger-Verlag, Berlin (1968).
- U. Canali:
  "MAC-RAD, A Reactor Shielding Code"
  EUR-2152 Euratom, Ispra, Italy (1964).
- E.P. Blizard et al.:
  "Reactor Handbook", Vol. III, Part B,
  Interscience Publishers, New York (1962).
- G. Birkoff et al.:
  "Alternating Direction Implicit Methods, Advances in Computers"
  Academic Press, New York (1962).
- J. Yamauchi et al.:
  "Numerical Calculation Methods for Computers"
  Baihukan, Tokyo (1967), in Japanese.
- I.I. Bondarenko:
  "Group Constants for Nuclear Reactor Calculations"
  Consultants Bureau, New York (1964).
NEA-0668/01, included references:
-  TRD-3, Two-dimensional Removal Diffusion Code for Shielding
   Calculation
   Contributed by Energy Research Laboratory
   Hitachi-shi, Ibaraki, Japan
-  Program TRD-3
   Note from NEA DATA BANK, March 1982
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11. MACHINE REQUIREMENTS

IBM 3033:
Main storage: 348 kbytes.
1 tape unit for output.
Disc storage:
   90 tracks for neutron flux
   20 tracks for removal neutron flux
    5 tracks for data library.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0668/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
OS370/033 VS2 03.8G (IBM 3033).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
The calculation is performed in 4500 steps.
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15. NAME AND ESTABLISHMENT OF AUTHOR

          Energy Research Laboratory
          Hitachi Ltd.
          Hitachi-shi
          Ibaraki
          Japan
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16. MATERIAL AVAILABLE
NEA-0668/01
File name File description Records
NEA0668_01.002 TRD-3 INFORMATION 45
NEA0668_01.003 TRD-3 SOURCE CARD IMAGE FORMAT FORTRAN-4 5100
NEA0668_01.004 TRD-3 OVERLAY CARDS 35
NEA0668_01.005 TRD-3 JCL FOR TEST CASES 30
NEA0668_01.006 TRD-3 INPUT FOR TEST CASE 285
NEA0668_01.007 TRD-3 OUTPUT OF TEST CASE 11115
NEA0668_01.008 TRD-3 LIBRARY DATA 803
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: gamma radiation, multigroup theory, neutron diffusion equation, neutron flux, shielding.