NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES

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Program name | Package id | Status | Status date |
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PALLAS-1D(VII) | NEA-1008/01 | Tested | 02-JUL-1987 |

Machines used:

Package ID | Orig. computer | Test computer |
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NEA-1008/01 | FACOM M-380 | IBM 3084 |

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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.

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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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.[ top ]

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.

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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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)

- 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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NEA-1008/01

To compile, linkedit and execute test case 1 of PALLAS on IBM 3084, 2500K bytes of main storage were required.[ top ]

NEA-1008/01

MVS (IBM 3084); VMS 4.4 (VAX-11/780).[ top ]

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NEA-1008/01

File name | File description | Records |
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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 |

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