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IAEA1242 UNF.

UNF, Multistep Compound Nucleus Neutron Cross-Sections and Spectra for Structural Materials

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1. NAME OR DESIGNATION OF PROGRAM:  UNF.
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2. COMPUTERS
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Program name Package id Status Status date
UNF IAEA1242/02 Arrived 23-MAY-2001

Machines used:

Package ID Orig. computer Test computer
IAEA1242/02 MICROVAX
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Based on a new semi-classical theory of multi-step nuclear reaction processes the code UNF code has been developed for calculations of fast neutron data for structural materials with neutron energies below 20 MeV. Besides the elastic scattering channel the code may handle decay sequences up to the (n,3n) reaction, including 14 reaction channels.
The energy spectra and double differential cross sections of all kinds of emitted particles as well as of the recoil nuclei can be obtained, Gamma production data, KERMAX factors and production spectra of n, p, alpha, deuteron, triton, helium-3 are also given. The output form is in the ENDF-6 format.
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4. METHOD OF SOLUTION:  Numerical integration is throughout Gaussian.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Incident neutron energies are from 1KeV to 20 MeV. There are 3 parameters in this code: Incident neutron energies NEL, the number of gamma ray spectra NGS (<200), the number of discrete levels of residual nuclei for the first particle emissions NLV. The user can set the values of NEL and NLV according to the storage size of the computer used. The number of discrete levels of residual nuclei for the multi-particle emissions is not greater than 20.
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6. TYPICAL RUNNING TIME

For the calculation of a whole set of fast neutron data for 56-FE En=8MeV: 40 seconds; En=14MeV: 300 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM:  Several files must be open for input and output options.
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8. RELATED AND AUXILIARY PROGRAMS

A code for automatic adjustment of  optical model parameters is needed in order to determine the optimal values of optical potential parameters as input to this code. If the direct scattering data and the direct reaction data are available from other codes, one can input the data so that the results will include the direct process effects.
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9. STATUS
Package ID Status date Status
IAEA1242/02 23-MAY-2001 Masterfiled Arrived
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10. REFERENCES

- Zhang Jingshan,
  A Semi-Classical Theory of Multi-Step Nuclear Reaction Processes
  to be published in Proc. Conf of Fast Neutron Physics BEIJING
  P.R. CHINA (1991).
IAEA1242/02, included references:
- Zhang Jingshang:
  Users Guide of UNF Code (May 1992).
- Zhang Jingshang:
  UNF Program of Fast Neutron Data Calculation for Structural
  Materials
  Reprint from Communications of Nuclear Data Programs, No. 7
  (1992), CNIC-00645 pages 14-33
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1242/02 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

        Zhang Jingshang
        1991 Chinese Nuclear Data Center
        Institute of Atomic Energy
        P.O. Box 275 (41)
        Beijing 102413 R.P. China
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16. MATERIAL AVAILABLE
IAEA1242/02
UNF.FOR UNF Source Program
UNF.DAT Input Data for UNF Code
TCF.DAT Test-Case Data Transmission coefficients data created by UNF code
DIR.DAT Direct inelastic and direct reaction data input
UNF.OUT Output example
report                   Users Guide (May 1992)                     REPPT
paper                    Reprint Comm.Nucl.Data Prog. (1992)        PAPPT
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17. CATEGORIES
  • A. Cross Section and Resonance Integral Calculations

Keywords: cross sections, elastic scattering, kerma factors, spectra.