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NEA-0461 STAPREF. (Abstract last modified 21-MAR-2000)


STAPREF, Nuclear Reactions Cross-Sections by Evaporation Model, Gamma-Cascades

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Abstract Table of Contents:

NAME | COMPUTER | PROBLEM | SOLUTION | RESTRICTIONS | CPU | FEATURES | AUXILIARIES | STATUS | REFERENCES | REQUIREMENTS | LANGUAGE | OPERATING SYSTEM | OTHER RESTRICTIONS | AUTHOR | MATERIAL | CATEGORIES |

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1. NAME OR DESIGNATION OF PROGRAM - STAPREF.


2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name         Package-ID  Status
STAPRE               NEA-0461/01 Obsolete
STAPRE               NEA-0461/02 Obsolete
STAPRE               NEA-0461/03 Obsolete
STAPREF              NEA-0461/04 Tested

Machines used:
Package-ID     Orig.Computer                       Test Computer
NEA-0461/04    IBM PC                              PC Pentium II 400

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.


4. METHOD OF SOLUTION - Integrations in connection with the evaporation formulas are approximated by summation over energy bins. For the gamma-ray cascades a recursion formula is employed. The width-fluctuation correction factor is calculated by use of Simpson's rule.


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.


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.

NEA-0461/04:

TYPICAL RUNNING TIME -
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.


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.


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.

NEA-0461/04:

RELATED OR AUXILIARY PROGRAMS -
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.


9. STATUS
NEA-0461/01: 04-SEP-1981 Obsolete
NEA-0461/02: 22-MAR-2000 Obsolete
NEA-0461/03: 22-MAR-2000 Obsolete
NEA-0461/04: 21-MAR-2000 Tested at NEADB


10. REFERENCES  - 
- M. Uhl:
  ACTA Phys. Austr. 31 (1970) 245.

NEA-0461/04:

REFERENCES  - 
- 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:
- Vladimir Maslov:
Manual on STAPREF code (Definition of Input and Output Files for Code STAPREF)


11. MACHINE REQUIREMENTS -

NEA-0461/04:

HARDWARE REQUIREMENTS - Program was installed on usual Pentium IBM PC, it was run on PC Pentium, 200MHz, 32 RAM, using Fortran 90 Lahey system.


12. PROGRAMMING LANGUAGE(S) USED -
NEA-0461/04: FORTRAN-90 


13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED -


14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - The program description contains instructions for segmentation in order to reduce storage requirements.


15. NAME AND ESTABLISHMENT OF AUTHOR -
STAPRE:
  M. Uhl
  Institut fuer Radiumforschung und Kernphysik
  Boltzmanngasse 3
  A-1090 Wien
  Austria
STAPREF:
  V.M. Maslov
  Radiation Physics and Chemistry Problems Institute,
  220109, Minsk-Sosny,
  Belarus


16. MATERIAL AVAILABLE -
NEA-0461/04:
stapref.for Fortran source file
pu239 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


17. CATEGORIES  - 

- A.  Cross Section and Resonance Integral Calculations


Keywords: CROSS SECTIONS, EMISSION SPECTRA, GAMMA RADIATION, NUCLEAR MODELS, STATISTICAL MODELS

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