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NEA-1008 PALLAS-1D(VII).

PALLAS-1D(VII), Direct Integration of Transport Equation in 1-D Planar and Spherical Geometry

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1. NAME OR DESIGNATION OF PROGRAM:  PALLAS-1D(VII).
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2. COMPUTERS
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Program name Package id Status Status date
PALLAS-1D(VII) NEA-1008/01 Tested 02-JUL-1987

Machines used:

Package ID Orig. computer Test computer
NEA-1008/01 FACOM M-380 IBM 3084
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3. DESCRIPTION OF PROGRAM OR FUNCTION

PALLAS-1D(VII) solves the steady state Boltzmann transport equation in one dimensional plan and spherical geometries for fixed source problems. It can also solve the transport of secondary gamma rays such as Bremsstrahlung and annihilation photons.
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4. METHOD OF SOLUTION

The method of direct integration of the transport equation is used, in which the equation is integrated along the flight path of radiation in the direction of motion at each discrete ordinate direction. Anisotropic scattering is treated  precisely using differential scattering cross sections for elastic scattering; however, isotropic scattering in the laboratory system is assumed in inelastic scattering of neutron. No iteration and convergence techniques are used for obtaining the flux. Energy dependence is treated by the multigroup approximation.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

PALLAS-1D(VII) has been written in the fixed dimensioning, which restricts the numbers  of energy meshes, material regions, nuclides, angular meshes, spatial meshes to be input.
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6. TYPICAL RUNNING TIME:
NEA-1008/01
NEA-DB ran test case 1 of this package on both an IBM 3084 and a VAX-11/780 computer. On IBM 3084, 423 CPU seconds were required to compile, linkedit and execute the problem.
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7. UNUSUAL FEATURES OF THE PROGRAM

Nuclear data for neutron and secondary gamma rays are read in from the PALLAS library tape (or disk). Data for reaction cross sections for calculation of neutron reactions are also read in from reaction rate library. Coefficients  for linear attenuation, pair production and photoelectric effect of  gamma rays are interpolated for specified energies from the PALLAS gamma-ray library in the code, where the data for discrete energies  from 0.01 to 20 MeV are given for the same nuclides and materials as those of neutrons.
Similarly, the flux to dose conversion factor for exposure dose, dose qeuivalent and absorbed dose also are interpolated.
The differential electron production cross sections relating to the  pair production reaction are calculated within the code, also the differential Bremsstrahlung gamma-ray production cross sections and  the stopping power are calculated within the code.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-1008/01 02-JUL-1987 Tested at NEADB
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10. REFERENCES

- R. Douglas O'Dell and Raymond E. Alcouffe:
  Transport Calculations for Nuclear Analyses: Theory and
  Guidelines for Effective Use of Transport Codes
  LA-10983-MS and UC-32 (September 1987)
NEA-1008/01, included references:
- K. Takeuchi and S. Tanaka:
  PALLAS-1D(VII): A Code for Direct Integration of Transport
  Equation in One-Dimensional Plane and Spherical Geometries.
  JAERI-M 84-214  (December 1984)
- K. Takeuchi and A. Yamaji:
  Neutron Transport Benchmark Calculations, (I) PALLAS Calculations
  Reprint from Journal of Nuclear Science and Technology, Vol. 11,
  No. 2, pp.49-57 (February 1974).
- K. Takeuchi:
  Numerical Solution to Space-Angle Energy-Dependent Neutron
  Integral Transport Equation
  Reprint from Journal of Nuclear Science and Technology, 8[3], pp.
  141-152 (March 1971).
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11. MACHINE REQUIREMENTS:
NEA-1008/01
To compile, linkedit and execute test case 1 of PALLAS  on IBM 3084, 2500K bytes of main storage were required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1008/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-1008/01
MVS (IBM 3084); VMS 4.4 (VAX-11/780).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

          Mr. K. Takeuchi
          Ship Research Institute
          Nuclear Ship Division
          6-38-1, Shinkawa
          Mitaka-Shi
          TOKYO
          Japan
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16. MATERIAL AVAILABLE
NEA-1008/01
File name File description Records
NEA1008_01.001 INFORMATION FILE 157
NEA1008_01.002 PALLAS FORTRAN FILE 5840
NEA1008_01.003 GAMMA RAY X SECTION LIBRARY 1135
NEA1008_01.004 NUCLEAR DATA FOR BREM. CALCULATIONS 317
NEA1008_01.005 REACTION RATE LIBRARY 01 LETHARGY 840
NEA1008_01.006 REACTION RATE LIBRARY 0.2 LETHARGY 448
NEA1008_01.007 REACTION RATE LIBRARY 0.4 LETHARGY 252
NEA1008_01.008 EFFECTIVE X SECTION LIB. 0.1 LETHARGY 71622
NEA1008_01.009 EFFECTIVE X SECTION LIB. 0.2 LETHARGY 25867
NEA1008_01.010 EFFECTIVE X SECTION LIB. 0.4 LETHARGY 10520
NEA1008_01.011 EFFECTIVE X SECTION LIB. 0.8 LETHARGY 4723
NEA1008_01.012 EFFECTIVE X SECTION LIB. 0.05 LETHARGY 21294
NEA1008_01.013 INFINITE X SECTION LIB. 0.1 LETHARGY 18410
NEA1008_01.014 INFINITE X SECTION LIB. 0.2 LETHARGY 14536
NEA1008_01.015 INFINITE X SECTION LIB. 0.4 LETHARGY 10462
NEA1008_01.016 INFINITE X SECTION LIB. 0.05 LETHARGY 50850
NEA1008_01.017 INFINITE X SECTION LIB. 0.8 LETHARGY 5131
NEA1008_01.018 SAMPLE INPUT CASE 1 37
NEA1008_01.019 SAMPLE INPUT CASE 2 19
NEA1008_01.020 SAMPLE OUTPUT CASE 1 4609
NEA1008_01.021 SAMPLE OUTPUT CASE 2 5097
NEA1008_01.022 SAMPLE JCL CARDS 171
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: anisotropic scattering, bremsstrahlung, discrete ordinate method, multigroup, neutron transport theory, photon transport, r-theta, x-y.