Computer Programs

DLC-0040 ZZ-LIB-IV.

DLC-0040 ZZ-LIB-IV.

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

NAME, COMPUTER, PROBLEM, SOLUTION, AUXILIARIES, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME

ZZ-LIB-IV.

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2. COMPUTERS

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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

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
FORMAT: Standard CCCC-III interface format.

NUMBER OF GROUPS: 50

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

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.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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 of 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 232Th, 233U, 235U, 238U, 239Pu, 240Pu, 241Pu.

A 50-group structure is used, with a thermal-1/E-fission weighting function. P0 through P3 matrices are provided when data permits.

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4. METHODS

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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8. RELATED OR 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.E. MacFarlane, R.M. Boicourt: NJOY: A Neutron and Proton Cross Section Processing System. Trans.Am.Nucl.Soc. no.22 p.702 (1975)

DLC-0040/01, included references:

- R.B. Kidman, R.E. MacFarlane:
LIB-IV, A Library of Group Constants for Nuclear Reactor Calculations
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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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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15. NAME AND ESTABLISHMENT OF AUTHORS

Los Alamos Scientific Laboratory

Los Alamos, NM 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

ZZZ. ARCHIVE

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