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PSR-0281 URR

URR, Cross-Sections, Selfshielding for Fertile and Fissile Isotopes in Unresolved Region

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1. NAME OR DESIGNATION OF PROGRAM:  URR
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2. COMPUTERS
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Program name Package id Status Status date
URR PSR-0281/01 Arrived 19-JAN-2000

Machines used:

Package ID Orig. computer Test computer
PSR-0281/01 DEC VAX 6000
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3. DESCRIPTION OF PROGRAM OR FUNCTION

URR was developed to calculate  cross-section probability tables, Bondarenko self-shielding factors, and self-indication ratios for fertile and fissile isotopes in the unresolved resonance region.
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4. METHOD OF SOLUTION

URR uses Monte Carlo techniques to select appropriate resonance parameters and to compute the cross sections at the desired reference energy. The neutron cross sections are calculated by the single-level Breit-Wigner formalism with s-, p-, and d-wave contributions. The cross-section probability tables are constructed by sampling the Doppler broadened cross-section. The various self-shielded factors are computed numerically as Lebesgue integrals over the cross-section probability tables.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME:  URR is interactive and executes in a few seconds.
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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
PSR-0281/01 19-JAN-2000 Masterfiled Arrived
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10. REFERENCES:
PSR-0281/01, included references:
- L.C. Leal, G. de Saussure and R.B. Perez:
  URR Computer Code - A Code to Calculate Resonance Neutron Cross
  Section Probability Tables, Bondarenko Self-shielding Factors and
  Self-Indication Ratios for Fissile and Fertile Nuclides
  ORNL/TM-11297 (August 1989).
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11. MACHINE REQUIREMENTS:  The code runs on any VAX computer.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0281/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The code was written in FORTRAN 77 and was tested on the VAX 6000 under the VMS operating system.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
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16. MATERIAL AVAILABLE
PSR-0281/01
source program   mag tapeURR FORTRAN Source (Compile,Link,execute)  SRCTP
test-case data   mag tapeURR Sample Input                           DATTP
test-case output mag tapeURR Sample Output                          OUTTP
report                   ORNL/TM-11297 (August 1989)                REPPT
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: Bondarenko scheme, breeding, fission, isotope production, isotopes, radioisotopes, resonance absorption, self-shielding, unresolved region.