IAEA1242 UNF.
UNF, Multistep Compound Nucleus Neutron Cross-Sections and Spectra for Structural Materials
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 |
|---|---|---|---|
| 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.
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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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.
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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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.
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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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).
- 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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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
Keywords: cross sections, elastic scattering, kerma factors, spectra.