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IAEA1177 UNIFY.

UNIFY, Fast Neutron Cross-Sections and Spectrum for Structural Materials

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1. NAME OR DESIGNATION OF PROGRAM:  UNIFY.
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2. COMPUTERS
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Program name Package id Status Status date
UNIFY IAEA1177/01 Arrived 19-JAN-2000

Machines used:

Package ID Orig. computer Test computer
IAEA1177/01 CDC CYBER 825
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Based on the unified model, the code UNIFY calculates fast neutron data for structural materials:
(1) Cross sections - Total cross sections for all types of reaction  channels; cross sections of discrete level and continuum emissions.
(2) Angular distribution - elastic scattering angular distributions  and its Legendre coefficients and transition matrix elements; Legendre coefficients of discrete levels in the inelastic scattering channels.
(3) Energy spectra
(4) Double differential cross sections of the inelastic and neutron  outgoing channels.
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4. METHOD OF SOLUTION

Gaussian integration is used for all numerical  integrations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

UNIFY can be used for neutron incident energies from 1 KeV to 20 MeV. Due to main storage limitations the number of incident energies could not exceed 50.
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6. TYPICAL RUNNING TIME

For En = 14 MeV: 200 seconds; En = 20 MeV: 500 seconds of CPU time were required. At lower energies, the calculations are quite fast.
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7. UNUSUAL FEATURES OF THE PROGRAM:  Several calculational and output options are available.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
IAEA1177/01 19-JAN-2000 Masterfiled Arrived
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10. REFERENCES:
IAEA1177/01, included references:
- Zhang Jingshang and Shi Xiangjun:
  The Formuation of "UNIFY" Code for the Calculation of Fast Neutron
  Data for Structural Materials
  INDC(CPR)-014/LJ (January 1989)
- Shi Xiangjun ans Zhang Jingshang:
  Description of UNIFY-ECN Code and the Guide for Users.
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1177/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

Extended memory may be used with: RFL EC=400. Depending on available storage, the parameters NEL and NLP may be set.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

         Shi Xiangjun and Zhang Jingshang
         Chinese Nuclear Data Center
         Institute of Atomic Energy
         P.O. Box 275 (41)
         BEIJING 102413
         P. R. China
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16. MATERIAL AVAILABLE
IAEA1177/01
source program   mag tapeUNIFY Source Program                       SRCTP
test-case data   mag tapeUNIFY Input Data                           DATTP
test-case output mag tapeUNIFY Output Data                          OUTTP
test-case data   mag tapeInput + Output Data                        DATTP
miscellaneous    mag tapeAbstract                                   MISTP
report                   INDC(CPR)-014/LJ (January 1989)            REPPT
report                   Descriptions of UNIFY-ECN & Guide for UsersREPPT
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17. CATEGORIES
  • A. Cross Section and Resonance Integral Calculations

Keywords: angular distribution, elastic scattering, fast neutrons, inelastic scattering, neutron cross sections, spectra.