NEA-0668 TRD-3.

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

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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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.