Computer Programs
DLC-0040 ZZ-LIB-IV.
last modified: 01-MAR-1977 | catalog | categories | new | search |

DLC-0040 ZZ-LIB-IV.

ZZ LIB-IV, 50-Group Cross-Section Library in CCCC-III Format from ENDF/B-IV for Fast Reactors

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-LIB-IV.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-LIB-IV DLC-0040/01 Tested 01-MAR-1977

Machines used:

Package ID Orig. computer Test computer
DLC-0040/01 Many Computers Many Computers
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3. DESCRIPTION OF PROBLEM OR FUNCTION


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  FORMAT: Standard CCCC-III interface format.

  NUMBER OF GROUPS: 50

NUCLIDES: Delayed neutron yields and spectra are provided for the seven isotopes Th-232, U-233, U-235, U-238, Pu-239, Pu-240, Pu-241.

ORIGIN: 90 materials of ENDF/B-IV plus the copper isotopes and lumped fission products of ENDF/B-III (total of 101 nuclides).

  WEIGHTING SPECTRUM: Thermal-1/E-fission.

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LIB-IV is a library of multigroup constants in standard CCCC-III interface format intended for (1) fast reactor core design, (2) CSEWG data testing and (3) processing code comparison.
It contains cross sections and self-shielding factors for all 90 materials of ENDF/B-IV plus the copper isotopes and lumped fission products of ENDF/B-III, making a total fo 101 nuclides. Data is available at zero degrees Kelvin and infinite dilution, plus three additional temperatures (300K, 900K, 2100K) and up to six additional values of sigma-zero. Delayed neutron yields and spectra are provided for the seven isotopes Th-232, U-233, U-235, U-238, Pu-239, Pu-240, Pu-241.

A 50-group structure is used, with a thermal-1/E-fission weight- ing function. P0 through P3 matrices are provided when data permits.
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4. METHOD OF SOLUTION

The library was generated from ENDF/B-IV data using the codes MINX (2) (PSR-0105), and NJOY (3) (PSR-0171).
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The utility programs LINX and BINX (4) (PSR-0117) can be used to merge CCCC files, or to convert between BCD and binary formats. CINX (5) (PSR-0117) collapses multi- group CCCC data sets to a coarser group structure.
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9. STATUS
Package ID Status date Status
DLC-0040/01 01-MAR-1977 Tested at NEADB
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10. REFERENCES

- R.B. Kidman, R.E. MacFarlane:
  LIB-IV, A Library of Group Constants for Nuclear Reactor Cal-
  culations
  LA-6260-MS (1976)
- C.R. Weisbin, P.D. Soran, R.E. MacFarlane, D.R. Harris, R.J.
  LaBauve, J.S. Hendricks, J.E. White, R.B. Kidman:
  MINX: A Multigroup Interpretation of Nuclear X-Sections from
  ENDF/B.
  LA-6486-MS (September 1976)
- R.E. MacFarlane, R.M. Boicourt:
  NJOY: A Neutron and Proton Cross Section Processing System.
  Trans.Am.Nucl.Soc. no.22 p.702 (1975)
- R.E. MacFarlane, R.B. Kidman:
  LINX and BINX: CCCC Utility Codes for the MINX Multigroup
  Processing Code.
  LA-6219-MS (February 1976)
- R.B. Kidman, R.E. MacFarlane:
  CINX: Collapsed Interpretation of Nuclear X-Sections.
  LA-6287-MX (April 1976)
DLC-0040/01, included references:
- R.B. Kidman, R.E. MacFarlane:
LIB-IV, A Library of Group Constants for Nuclear Reactor Cal
culations
LA-6260-MS (1976)
- J.E. White and R.W. Roussin:
Informal Notes, IBM-360 Versions of the BINX, LINX, and CINX
Utility Codes (March 1977)
- R.B. Kidman, R.E. MacFarlane:
CINX: Collapsed Interpretation of Nuclear X-Sections.
LA-6287-MX (April 1976)
- R.E. MacFarlane, R.B. Kidman:
LINX and BINX: CCCC Utility Codes for the MINX Multigroup
Processing Code.
LA-6219-MS (February 1976)
- R.B. Kidman:
ENDF/B-IV, LIB-IV, and the CSEWG Benchmarks
LA-7355-MS (june 1978)
- C.R. Weisbin, P.D. Soran, R.E. MacFarlane, D.R. Harris, R.J.
LaBauve, J.S. Hendricks, J.E. White, R.B. Kidman:
MINX: A Multigroup Interpretation of Nuclear X-Sections from
ENDF/B.
LA-6486-MS (ENDF-237) (September 1976)
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Los Alamos Scientific Laboratory
Los Alamos, Mew Mexico 87545, U.S.A.
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16. MATERIAL AVAILABLE
DLC-0040/01
File name File description Records
DLC0040_01.001 INFORMATION 1
DLC0040_01.002 ISOTXS MICROSCOPIC GROUP NEUTRON XSECTIONS 192273
DLC0040_01.003 BRKOXS BONDARENKO SELF SHIELDING TABLES 80083
DLC0040_01.004 DLAYXS DELAYED NEUTRON YIELDS AND SPECTRA 735
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17. CATEGORIES
  • C. Static Design Studies
  • Z. Data.

Keywords: ENDF/B, data, delayed neutrons, fast reactors, fission products, group constants, multigroup, self-shielding.