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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. Only liaison officers are authorised to submit online requests. Rules for requesters 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 item found

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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.