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IAEA0901 IPEET-103.

IPEET-103, Neutron Induced Reaction Cross-Sections for Fissile Nuclides, Preequilibrium Model

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1. NAME OR DESIGNATION OF PROGRAM:  IPEET-103.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
IPEET-103 IAEA0901/01 Tested 08-DEC-1987

Machines used:

Package ID Orig. computer Test computer
IAEA0901/01 CDC CYBER 825 CDC CYBER 740
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3. DESCRIPTION OF PROGRAM OR FUNCTION

This code is used to calculate  the cross sections and the secondary neutron spectra for fissile nuclei induced by 3-20 MeV neutrons. The theoretical model used in calculation is the evaporation model including the preequilibrium statistical theory based on the exciton model, in order to fit the experiment data well, the level density of the saddle point state uses the single sharp barrier approximation and its fitting parameters, K1 and K2, are introduced, when the experiment data of fission cross sections are input, K1 and K2 is adjusted automatically. The calculated results include the cross sections for (n,r), (n,n'), (n,2n), (n,3n), (n,f), (n,n'f), (n,2nf) channels and  the normalized secondary neutron spectra.
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4. METHOD OF SOLUTION

The two-dimension optimum seeking method, is adopted for the adjustment of K1 and K2. The Gaussian's twenty point integration method is used for numerical intergrations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

   1) The calculations are restricted to the actinides.
   2) The energy range of incident neutrons is restricted to from 3
      to 20 MeV and the energy point number is 25.
3) The number of outgoing energies for calculated secondary       neutrons is 38.
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6. TYPICAL RUNNING TIME

The running time is about 450 CPU seconds for calculating the whole set of data, but if the secondary neutron spectra is not needed, the running time is about 100 CPU seconds only.
IAEA0901/01
NEA-DB executed the test case included in this package  on a CDC CYBER 740 computer in 467 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
IAEA0901/01 08-DEC-1987 Tested at NEADB
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10. REFERENCES

- Zhang Jingshang et al.,
  "The Statistical Theoretical Calculation of the Fissile Nuclei
  Reaction induced by 3 20 MeV Neutron" (in Chinese)
  (HSJ-78227) (11JS) 226(1980).
- Wang Shunuam et al.,
  "Calculation and Analysis of Reaction Cross Sections and Energy
  Spectra of Fissile Nuclei induced by 3 20 MeV Neutron"
  (in Chinese).
  Proceedings of the Fourth Nuclear Data Conference of China, 1985.
- A. Gilbert, A.G.W. Cameron,
  Can. J.Phys., 43, 1446(1967).
- E.J. Lynn,
  AERE-R7468, (1974).
- J.J. Griffin,
  Phys. Rev. Lett., 17, 478(1966).
- M. Buhning,
  Nucl. Phys., A152, 529(1970).
- Kalbach Cline,
  Nucl. Phys. A210, 590(1973).
- J.L. Cook,
  Aust. J. Phys., 20, 477(1967).
IAEA0901/01, included references:
- NEA Data Bank:
  How to Use for IPEET-103.
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11. MACHINE REQUIREMENTS:
IAEA0901/01
To run the test case included in this package on a CDC CYBER 740 computer, 73100 (octal) words of main storage were required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0901/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  NOS (Network Operating System).
IAEA0901/01
NOS2.5.1 664/650 (CDC CYBER 740).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

1) The file, F1, for input parameters and the evaluated  experimental data is set up with required order before       calculation and output data is stored in the file F2.
2) If calculation is needed for the incident neutron energy range       of 0.001-3 MeV, the LIANG code can be used.
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15. NAME AND ESTABLISHMENT OF AUTHORS

         Zhang Jingshang, Wang Shunuan
         Yang Shiwei, Shi Xiangjun
         Chinese Nuclear Data Center
         Beijing, P.R. of CHINA
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16. MATERIAL AVAILABLE
IAEA0901/01
File name File description Records
IAEA0901_01.001 Information File 42
IAEA0901_01.002 Control.Information and JCL 12
IAEA0901_01.003 IPEET-103 Source Program 1489
IAEA0901_01.004 IPEET-103 Sample Problem Input 25
IAEA0901_01.005 IPEET-103 Sample Problem Output 2731
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17. CATEGORIES
  • A. Cross Section and Resonance Integral Calculations

Keywords: evaporation model, fission spectra, neutron cross sections.