NEA-0461 STAPREF.
STAPREF, Nuclear Reactions Cross-Sections by Evaporation Model, Gamma-Cascades
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| STAPREF | NEA-0461/04 | Tested | 21-MAR-2000 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0461/04 | IBM PC | PC Pentium II 400 |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
Calculation of energy-averaged cross sections for nuclear reactions with emission of particles and gamma rays and fission. The models employed are the evaporation model with inclusion of pre-equilibrium decay and a gamma-ray cascade model. Angular momentum and parity conservation are accounted for.
Major improvement in the original 1976 STAPRE program by M. Uhl relates to level density approach, implemented in subroutine ZSTDE. Generalized superfluid model is incorporated, boltzman-gas modeling of intrinsic state density and semi-empirical modeling of a few-quasiparticle effects in total level density at equilibrium and saddle deformations of actinide nuclei.
Calculation of energy-averaged cross sections for nuclear reactions with emission of particles and gamma rays and fission. The models employed are the evaporation model with inclusion of pre-equilibrium decay and a gamma-ray cascade model. Angular momentum and parity conservation are accounted for.
Major improvement in the original 1976 STAPRE program by M. Uhl relates to level density approach, implemented in subroutine ZSTDE. Generalized superfluid model is incorporated, boltzman-gas modeling of intrinsic state density and semi-empirical modeling of a few-quasiparticle effects in total level density at equilibrium and saddle deformations of actinide nuclei.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
Only particle induced reactions can be treated. The number of sequentially emitted particles is limited to 6, while the number of gamma rays is arbitrary. Angular distributions of emitted particles and photons are not calculated.
STAPREF: The number of sequentially emitted particles could be easily extended up to, say, 30 by increasing the array dimensions to cover incident particle energy range up to 150 MeV.
Only particle induced reactions can be treated. The number of sequentially emitted particles is limited to 6, while the number of gamma rays is arbitrary. Angular distributions of emitted particles and photons are not calculated.
STAPREF: The number of sequentially emitted particles could be easily extended up to, say, 30 by increasing the array dimensions to cover incident particle energy range up to 150 MeV.
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6. TYPICAL RUNNING TIME
The calculation of the excitation function (1 < e (in) < = 20 MeV, 1 MeV steps) for a typical, neutron induced reaction requires a few seconds on workstations.
The calculation of the excitation function (1 < e (in) < = 20 MeV, 1 MeV steps) for a typical, neutron induced reaction requires a few seconds on workstations.
NEA-0461/04
The calculation of cross sections at 77 energy points in the neutron energy range from 1 MeV up to 20 MeV for actinide nucleus requires 50 sec. on IBM PC Pentium 200Pro.
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7. UNUSUAL FEATURES OF THE PROGRAM
In addition to the activation cross sections, particle and gamma ray production spectra are calculated. Isomeric state populations and production cross sections for gamma rays from low excited levels are obtained, too. For fission a single or a double humped barrier may be chosen.
In addition to the activation cross sections, particle and gamma ray production spectra are calculated. Isomeric state populations and production cross sections for gamma rays from low excited levels are obtained, too. For fission a single or a double humped barrier may be chosen.
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8. RELATED AND AUXILIARY PROGRAMS
Since transmission coefficients are needed as input data for the code STAPRE, it is advantageous to have an optical model code at one's disposal to generate these quantitites.
Since transmission coefficients are needed as input data for the code STAPRE, it is advantageous to have an optical model code at one's disposal to generate these quantitites.
NEA-0461/04
Optical model code (ECIS, SCAT or other), preferably coupled channel one, should be used to supply transmission coefficients for incident particle.DATA LIBRARY:
tl.p39: particle transmission coefficients from deformed or spherical optical model calculations.
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NEA-0461/04, bibliography:
- V. M. Maslov:Fission Level Density and Barrier Parameters for Actinide Neutron-Induced Cross Section Calculations
INDC(BLR)-13, 1998, Vienna.
- V.M. Maslov, Yu.V. Porodzinskij, A. Hasegawa et al.:
Neutron Data Evaluation of 238-U, JAERI-Research 98-040, 1998.
NEA-0461/04, included references:
- Vladimir Maslov:Manual on STAPREF code (Definition of Input and Output Files for Code STAPREF)
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NEA-0461/04
Program was installed on usual Pentium IBM PC, it was run on PC Pentium, 200MHz, 32 RAM, using Fortran 90 Lahey system.[ top ]
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NEA-0461/04
stapref.for Fortran source filepu239 Input file
tl.p39 Auxiliary input file
staptcs.in Auxiliary file
st.out Output file
ngraf.out Output file
stapcomp File used to compile stapref.for fortran source file
staplink File used to produce stapref.exe module
absstap.doc Program abstract
vvod.doc Manual for the STAPREF program
vvod.pdf Manual in PDF
Keywords: cross sections, emission spectra, gamma radiation, nuclear models, statistical models.