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RSIC DATA LIBRARY DLC-075

1. NAME AND TITLE OF DATA LIBRARY

BUGLE-80: Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

BCBN: BCD to binary conversion program.

3. CONTRIBUTORS

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

ANS-6.1.2.

EG&G Idaho, Inc., Idaho Falls, Idaho.

Battelle, Columbus, Ohio.

4. HISTORICAL BACKGROUND AND INFORMATION

The 47 neutron, 20 gama-ray group, P3, cross section library was developed at Oak Ridge National Laboratory for LWR shielding applications. It replaces the DLC-47/BUGLE library which was prepared for use by the ANS 6.1.2 Working Group on Shielding Cross Sections for concrete shielding applications. Studies by members of ANS 6.1.2 and others led to the development of BUGLE-80. Since it has a different group structure, BUGLE-80 was given a new DLC number to help minimize confusion with the earlier version.

The current library was generated by collapse from DLC-41C/VITAMIN-C using a spectrum typical to that expected in a PWR shield. The cross sections should be useful for shielding situations where resonance self shielding and temperature effects are not important.

5. APPLICATION OF THE DATA

The DLC-75/BUGLE-80 package contains microscopic coupled (47n,20g) data for 42 isotopes and 47n data for 24 isotopes (gamma-production not available on ENDF/B-IV for these 24 isotopes). In addition, sample input and output for running ANISN test cases for a concrete and LWR problem in both (47n,20g) and (171n,36g) energy structures are also provided. Kerma factors in the 47n,20g structure (based on DLC-60/MACKLIB-IV) are included as well as (47n,20g) cross sections with delayed gammas from fission for U-235, U-238, and Pu-239.

6. SOURCE AND SCOPE OF DATA

The library was produced in a manner similar to that for BUGLE. The VITAMIN-C library was the starting point for the series of AMPX-II steps followed by an AXMIX run that were required to make BUGLE-80. A calculational scheme was used to produce the 19 materials used in the concrete and LWR calculations.

BUGLE-80 is based on ENDF/B-IV evaluated data and the group structure has been tailored to represent the spectral phenomena of typical LWR shielding problems. It was derived by collapsing from DLC-41/VITAMIN-C. The evaluated data which served as sources of data for VITAMIN-C are ENDF/B-IV, LENDL, and ENDF/B-III.

47 neutron, 20 gamma-ray group, P3, cross sections (microscopic and macroscopic cross sections used in the concrete and LWR calculations.)

1H, 10B, 16O, Cr, 55Mn, Fe, Ni, Zr, 235U, 238U, 12C, Si, Mo, Na, Mg, 27Al, 32S, K, Ca.

47 neutron 20 gamma-ray group, P3, cross sections.

6Li, 7Li, 9Be, 14N, F, 31P, Cl, Ti, V, 59Co, Cu, 93Nb, Sn, Ba, 151Eu, 153Eu, 181Ta, 182W, 183W, 184W, 186W, Pb, 239Pu, 240Pu.

47 neutron group, P3, cross sections (23 materials) (neutron only).

234U, 236U, 242Pu, 233Pa, Gd, 243Am, 244Cm, 241Am, 238Pu, 241Pu, 3H, 3He, 4He, 2Zirc, 107Ag, 109Ag, Cd, 232Th, 233U, 237Np, 2H, 11B.

47 neutron, 20 gamma-ray group kerma factors from MACKLIB-IV (49 materials).

1H, 4He, 6Li, 7Li, 9Be, 10B, 11B, C, 14N, 16O, F, 23Na, Mg, 27Al, Si, Cl, K, Ca, Ti, V, Cr, 55Mn, Fe, 59Co, Ni, Cu, Nb, Mo, 181Ta, 182W, 183W, 184W, Pb, 232Th, 233Pa, 233U, 234U, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am.

47 neutron, 20 gamma-ray group, P3, cross section with delayed gammas from fission.

235U, 238U, 239Pu.

In October 1992 versions B & C were updated with the addition of bismuth, deuterium and cadmium, which were collapsed from the ENDF/B-V derived DLC-113/VITAMIN-E Library.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

BCBN is included to read formatted ANISN records and write them as unformatted records; the code is called BCD2BIN for the PC 386 and PC 486 (version B).

8. DATA FORMAT AND COMPUTER

Card images in ANISN format; mainframe computers with a subset distributed on diskettes; The entire package has been downloaded to diskettes for use on 386/387 personal computers.

9. TYPICAL RUNNING TIME

On a PC 386, the BCD2BIN program took about 4 minutes to convert XSEC1.BCD to binary form.

10. REFERENCE

R. W. Roussin, "BUGLE-80: A Coupled 47-Neutron, 20-Gamma-Ray Group Library for LWR Shielding Calculations," Informal Notes (June 1980).

11. CONTENTS OF LIBRARY

Included are the referenced documents and one of the following packages:

Version A - (D00075I303300) - released July 1980 - on 1 tape cartridge in tar format.

Includes sample cases, BCD to binary conversion program,

JCL files, plus the following data files in ANISN format:

47n, 20g, P3 cross sections for 48 materials and mixtures.

47n, P3 cross sections for 23 materials.

171n, 36g, P3 macroscopic x-sections for concrete & LWR problems.

47n, 20g kerma factors from MACKLIB-IV for 49 materials.

47n, 20g, P3 x-sections with delayed gammas from fission.

Version B - (D00075PC38601) - released April 1991 - on 2 DS/HD diskettes - contains all files

from Version A with BCD to binary conversion program for PC.

Updated October 1992 with addition of H-2, Cd, & Bi-209.

Version C - (D00075IBMPC02) - released July 1989 - on 1 DS/HD diskette - subset.

Contains files 1 & 2 of Version A in ANISN format.

47n, 20g, P3 cross sections for 48 materials and mixtures.

The data are in 192 separate files.

Updated October 1992 with addition of H-2, Cd, & Bi-209.

Version D - (D00075IBMPC03) - released July 1989 - on 1 DS/HD diskette - subset.

Contains files 1 & 2 of Version A in ISOTXS format.

47n, P3 cross sections for 48 materials and mixtures.

The data are in 48 separate files.

October 1992 updates:

This ENDF/B-IV derived, 47n, 20g, P3 data package was updated with the addition of data for bismuth, deuterium and cadmium. The new data were collapsed from the DLC-113/VITAMIN-E library, which is based on ENDF/B-V and added to versions (B) and (C).

The new data are distributed in compressed form in file BUGADD.EXE.

You need to decompress the '*.EXE' file (files).

The compression was performed using the programs of PKware, Inc., Brown Deer, Wisconsin

These programs are distributed as 'shareware'.

12. DATE OF ABSTRACT

April 1985, revised August 1989, April 1991, November 1993.

KEYWORDS: ANISN FORMAT; BENCHMARK PROBLEM CROSS SECTIONS; CONCRETE CROSS SECTIONS; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MICROCOMPUTER; MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; CCCC INTERFACE FORMAT