1. NAME AND TITLE OF DATA LIBRARY

CLEAR: 126 Neutron, 36 Gamma-Ray Cross Sections in AMPX and CCCC Interface Formats for LMFBR Neutronics Calculations.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is included in the package.

3. CONTRIBUTOR

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

4. HISTORICAL BACKGROUND AND INFORMATION

DLC-42/CLEAR was reorganized by removing the AMPX modules and CCCC interface handling codes from the package. The sample problems are designed to be executed using PSR-117/MARS. The change was made to try to minimize the updating required when a change is made to a retrieval code needed by a particular DLC. PSR-117 is designed to be used with several DLCs now such a DLC-41, -42, and -43.

The revised package is designated DLC-42B. It corresponds to DLC-41B /VITAMIN-C and DLC-53/VITAMIN-4C in data content and was derived from the above by collapsing appropriate files from 171 to 126 neutron groups. Users should watch the RSIC Newsletter for update announcements for the data in DLC-42 or for changes in the retrieval codes in PSR-117/MARS.

5. APPLICATION OF THE DATA

Specifications are presented for pseudo-composition independent fine-group and broad-group LMFBR neutron-gamma libraries. A one-dimensional cylindrical model of the CRBRP is used to derive the fine- and broad-group composition-dependent data. Energy boundary selection was guided by sensitivity considerations and compatibility with previously existing multigroup sets. Fast reactor data testing of CSEWG benchmark critical assemblies is summarized.

6. SOURCE AND SCOPE OF DATA

Three forms of cross-section information will be available to the user. The first and most general form (Form 1) consists of data in three formats in addition to a Bondarenko interpolation code, a neutron-gamma coupling code, and a format converter. The second form (Form 2) is used for the one-dimensional cylindrical model with a buckling search on k being critical. It was generated for CRBR core and shield analysis requirements at ORNL and will be available upon request. Form 3 is Broad-Group Composition Libraries generated by collapsing techniques. It was generated for internal ORNL analysis needs but is available on request.

126 Neutron Group ISOTXS Master, 126 Neutron Group BRKOXS Master, and 126 Neutron Group AMPX Master (61 Materials) for the IBM 360/91 computer:

Mo, ²⁴¹AM, ²³⁸Pu, ²⁴¹Pu, ⁹Be, Na, Ca, Fe, ²³⁵U, ²³⁸U, ²³⁹Pu, K, ¹²C, ¹H, ¹¹B, ²⁷Al, Si, ²⁴⁰Pu, ²³⁶U, Ni, ⁵⁵Mn, Cr, ¹⁶O, ²³⁴U, ²⁴²Pu, ⁹³Nb, ⁶Li, ⁷Li, Pb, ¹⁴N, Mg, 2H, V, F, Cu, ¹⁰B, ³H, ⁴He, ³¹P, ³²S, Ti, ⁵⁹Co, Zirc, ^ZrNat, ¹⁰⁷Ag, ¹⁰⁹Ag, Cd, Sn, ³He, Ba, ¹⁵¹Eu, Cl, ¹⁵³Eu, ¹⁸⁵Ta, ¹⁸²W, ¹⁸³W, ¹⁸⁴W, ¹⁸⁶W, ²³⁷Np, ²³²Th, ²³²U.

126 Neutron, 36 Gamma-Ray Group LAPHNGAS AMPX Interface (43 Materials):

¹⁰B, ⁵⁹Co, ³¹P, ³²S, ^NatZr, ^NatSn, ¹³⁸Ba, Cl, 14N, ¹⁸¹Ta, ¹⁵¹Eu, ¹⁵³Eu, ¹⁸²W, ¹⁸³W, ¹⁸⁴W, ¹⁸⁶W, ²³⁹Pu, ²⁴⁰Pu, ²³⁵U, ²³⁸U, Mo, Na, 16O, Fe, Cr, Ni, ⁵⁵Mn, Si, ¹H, Be, ²⁷Al, K, ¹²C, ⁹³Nb, ⁶Li, ⁷Li, Pb, Mg, Ca, F, Ti, V, Cu.

36 Gamma-Ray Group SMUG AMPX Interface (40 Materials):

H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zr, Nb, Mo, Ag, Cd, Sn, Eu, Ta, W, Pb, Th, U, Pu, Cl, Ba.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

EBCDIC card images; IBM 360/91.

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

C. R. Weisbin, R. W. Roussin, J. E. White, and R. Q. Wright, "Specification for Pseudo-Composition-Dependent Fine- and Broad-Group LMFBR Neutron-Gamma Libraries at ORNL," ORNL-TM-5142 (December 1975).

J. E. White and R. Q. Wright, "Sample Problems for DLC-42B/CLEAR," Presented at the RSIC Workshop on Multigroup Cross-Section Handling Codes (March 1975).

11. CONTENTS OF LIBRARY

Included are the referenced documents and one tape cartridge in TAR format which contains the neutron group cross sections, gamma-ray group D interface format, and gamma-ray cross section interface format, plus output from the sample problems.

12. DATE OF ABSTRACT

December 1984.

KEYWORDS: AMPX INTERFACE FORMAT; GAMMA-RAY PRODUCTION DATA; MULTIGROUP CROSS SECTIONS