Computer Programs
NESC0184 THERMOS-BRT-1.
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NESC0184 THERMOS-BRT-1.

THERMOS-BRT-1, 1-D Integral Transport for Neutron Spectra, Slab and Cylinder

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1. NAME OR DESIGNATION OF PROGRAM

THERMOS-BRT1

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2. COMPUTERS

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Program name Package id Status Status date
THERMOS-BRT-1 NESC0184/01 Tested 01-APR-1973

Machines used:

Package ID Orig. computer Test computer
NESC0184/01 IBM 370 series IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION

BRT1, like the original THERMOS code developed by H. Honeck of Brookhaven National Laboratory, computes the scalar thermal neutron spectrum as a function of position in a lattice by solving the integral transport equation with isotropic scattering. One-dimensional slab or cylindrical geometry may be used. As output the code supplies flux-averaged values of sigma a, sigma f, nu sigma f, sigma s, and d for the cell composition and the values of sigma a, sigma f, nu sigma f, sigma s, and sigma tr for the isotopic constituents.

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4. METHOD OF SOLUTION

The method used in solving the transport integral equation is the power iteration method. To accelerate convergence the code uses a combination of Gauss iteration, renormalization, over-relaxation, and extrapolation procedures.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of

  • 30 speed groups

  • 30 space points

  • 30 isotopes in mixture

  • 30 isotopes in the edit

  • 8 mixtures

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6. TYPICAL RUNNING TIME

The sample problem is a 2-region slab and is solved using 10 space points and 30 speed groups. There are two mixtures used. Five materials are used in the cell and one in the edit. The time in general is a function of the number of space points and energy groups used by the problem.

Typical running time for BRT1 with the random access library is one minute with a reflecting boundary condition and 30 seconds with a white boundary condition. Succeeding cases require approximately 15 seconds each.

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7. UNUSUAL FEATURES OF THE PROGRAM

In BRT1 options include the white boundary condition, current calculation, transverse buckling, linear anisotropic scattering correction, and smeared cell punched output for use as region input to a succeeding case. Random access library data can be stored on drum or disk.

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8. RELATED AND AUXILIARY PROGRAMS

RLITHE updates and/or prints the BRT data tape or random access data.

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9. STATUS
Package ID Status date Status
NESC0184/01 01-APR-1973 Tested at NEADB
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10. REFERENCES
  • H.C. Honeck: A Thermalization Transport Theory Code for Reactor Lattice Calculations, BNL-5826 (September 1961).

  • H.C. Honeck: The Distribution of Thermal Neutrons in Space and Energy in Reactor Lattices Part 1 – Theory Nuclear Science and Engineering, p. 193 (1960).

  • D.R. Skeen and L.J. Page: THERMOS/Battelle..The Battelle Version of the THERMOS Code, BNWL-516 (June 1967).

NESC0184/01, included references:
- C.L. Bennett and W.L. Purcell:
  BRT-I Battelle Revised THERMOS
  BNWL-1434 (June 1970).
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11. MACHINE REQUIREMENTS

64K memory, input, output, program, library, and punch units plus 3 scratch units or equivalent drum storage.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0184/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

CSCX.

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15. NAME AND ESTABLISHMENT OF AUTHORS

C. L. Bennett and W. L. Purcell

Reactor Physics Department

Pacific Northwest Laboratories

Battelle

P. O. Box 999

Richland, Washington 99352

USA

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16. MATERIAL AVAILABLE
NESC0184/01
File name File description Records
NESC0184_01.001 RLITHE SOURCE PROGRAMME 494
NESC0184_01.002 RLITHE LIBRARY INPUT DATA 7450
NESC0184_01.003 BRT-1 SOURCE PROGRAMME 2571
NESC0184_01.004 BRT-1 JCL+OVERLAY CARDS+SAMPLE INPUT 39
NESC0184_01.005 RLITHE PRINT OUT OF THE LIBRARY 4968
NESC0184_01.006 BRT-1 SAMPLE OUTPUT 547
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: cross sections, cylinders, neutron spectra, one-dimensional, reactor lattices, scattering, slabs, thermal neutrons, transport theory.