last modified: 02-DEC-1983 | catalog | categories | new | search |

DLC-0076 ZZ-SAILOR.

ZZ SAILOR, 47 Neutron-20 Gamma-Group Coupled Cross-Section Library from VITAMIN-C by AMPX

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-SAILOR.
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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
ZZ-SAILOR DLC-0076/01 Tested 02-DEC-1983

Machines used:

Package ID Orig. computer Test computer
DLC-0076/01 IBM 3081 IBM 3081
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3. DESCRIPTION OF PROBLEM OR FUNCTION


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  FORMAT: ANISN

  NUMBER OF GROUPS: 47-neutron and 20-gamma-ray group structure.

NUCLIDES: Li, B, Th, U, Np, Pu, Al, S, Ti, Mn, Fe, Co, Ni, Cu, In,  I, Sc, Na, Au.

  ORIGIN: VITAMIN-C

  WEIGHTING SPECTRUM: flat

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ZZ-SAILOR is a data library of coupled self-shielded neutron cross sections in 47-neutron and 20- gamma-ray group structure. It can be used for a wide range of radiation transport problems associated with pressurized-water and boiling-water reactors.
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4. METHOD OF SOLUTION

The VITAMIN-C cross section library (DLC-0041)  was processed by various modules of the AMPX-III system in different execution sequences.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

NEA-DB executed the test case of the BCD-to-  BIN conversion program on IBM 3081 in 21.7 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
DLC-0076/01 02-DEC-1983 Tested at NEADB
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10. REFERENCES:
DLC-0076/01, included references:
- G.L. Simmons:
  Analysis of the Browns Ferry Unit 3 Irradiation Experiments.
  EPRI NP-3719  (November 1984)
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11. MACHINE REQUIREMENTS

To execute the test case of the conversion program on IBM 3081, 292K bytes of main storage are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0076/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The conversion program was executed under MVS-SP (IBM 3081).
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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:   Science Applications, Inc., La Jolla, California.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Electric Power Research Institute, Palo Alto, California.
Battelle, Columbus, Ohio.
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16. MATERIAL AVAILABLE
DLC-0076/01
File name File description Records
DLC0076_01.003 ZZ-SAILOR INFORMATION FILE 27
DLC0076_01.004 ZZ-SAILOR JCL FOR TEST CASE EXECUTION 62
DLC0076_01.005 BCD-BIN CONVERSION PROGRAM (FORTRAN-4) 140
DLC0076_01.006 X-SEC LIBRARY DATA FOR LWR CALCULATIONS 40702
DLC0076_01.007 BCD-BIN CONVERSION PROGRAM INPUT DATA 1
DLC0076_01.008 BCD-BIN CONVERSION PROGRAM PRINTED OUTPUT 234
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17. CATEGORIES
  • C. Static Design Studies
  • Z. Data.

Keywords: BWR reactors, LWR reactors, coupled neutron gamma cross sections, cross sections, data library, group constants, pwr reactors, shielding.