RSICC DATA LIBRARY DLC-076
1. NAME AND TITLE OF DATA LIBRARY
SAILOR: Coupled, Self-Shielded, 47 Neutron, 20 Gamma-Ray, P3, Cross Section Library for Light Water Reactors. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
BCDBIN: Conversion Program to Make an ANISN Library.
3. CONTRIBUTORS
Science Applications, Inc., La Jolla, California.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Electric Power Research Institute, Palo Alto, California.
Battelle, Columbus, Ohio.
4. HISTORICAL BACKGROUND AND INFORMATION
The ANS 6.1.2 Working Group developed a Standard for specification of a multigroup cross-section library for LWR shielding applications. The DLC-47/BUGLE library, produced by collapse from DLC-41/VITAMIN-C, was the first attempt at providing a library that conformed. Comparison of BUGLE results with several multigroup libraries for a concrete slab problem and an LWR model revealed deficiencies that limited its usefulness as a cross-section library for use in various LWR shielding applications.
It was recognized that changes to the group structure, self shielding appropriate to specific geometries and compositions, proper treatment of temperature effects, and collapse with appropriate energy spectra would be required to develop a broad group library for application to specific LWR problems. From this perspective, a multigroup cross section library called SAILOR (Shielded and Application Independent Libraries for Operating Reactors) was developed. The DLC-75/BUGLE80 library, which used the same group structure as SAILOR, was ultimately cited in the ANS 6.1.2 Standard. Delay in the release of SAILOR precluded its inclusion in the Standard.
5. APPLICATION OF THE DATA
One-dimensional cylindrical models of a Pressurized Water Reactor (PWR) and a Boiling Water Reactor (BWR) were used as the focal point for the determination of reference spectra. These calculated spectra were then used in making comparisons between various cross section libraries and also as the source of weighting spectra for collapsing the VITAMIN-C library. The models were used to represent conditions at the reactor mid-plane and served as the basis for determining the neutron and gamma-ray spectra at various radial locations. The BWR model consisted of seven concentric regions and the PWR model eight. It is expected that actual reactors with configurations near that of the SAILOR models can be analyzed well with this library.
6. SOURCE AND SCOPE OF DATA
Data are provided for the range of materials needed in the analysis of LWR shielding applications, including the pressure vessel dosimetry problem. Microscopic cross sections for individual elements and isotopes are provided for each region of the PWR and BWR models. These transport cross sections are based on self-shielded data collapsed from DLC-41/VITAMIN-C (based on ENDF/B-IV) AMPX-II system. In addition, dosimetry cross sections from ENDF/B-IV are also included.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
BCDBIN program has the single purpose of converting the card image form of the SAILOR cross-section library into the unformatted form that is known as an ANISN Library.
8. DATA FORMAT AND COMPUTER
BCD/EBCDIC card images; IBM 370/3033, PC 386, PC 486.
9. TYPICAL RUNNING TIME
Conversion takes less than one minute on an IBM 3033. On a PC 386 the conversion program took about 9 minutes.
10. REFERENCES
a. Included with package:
G. L. Simmons, "Analysis of the Browns Ferry Unit 3 Irradiation Experiments," EPRI NP-3719 (November 1984).
b. Background information:
American Nuclear Society Standards Committee Working Group ANS-6.1.2, "American National Standard Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants," ANSI/ANS-6.1.2-1983 (August 1983).
11. CONTENTS OF LIBRARY
Included are the document in (10.a) and one (1.2MB) DOS diskette which contains the cross sections, the input data for BCDBIN, and the printed output from BCDBIN. The PC 386 and PC 486 version is available on two DS/HD 5.25-inch diskette (1.2 MB).
12. DATE OF ABSTRACT
April 1985; July 1987; April 1991.
KEYWORDS: ANISN FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MICROCOMPUTER; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B