1. NAME AND TITLE OF DATA LIBRARY
EURLIB: 100 Neutron, 20 Gamma-Ray Group Cross Section Library for Use in the
European Shielding Benchmark Program.
2. DATA AND TITLE OF DATA RETRIEVAL PROGRAM
DLC-2 CODE: Converts library from card image to binary ANISN format.
ESIS, Ispra, Italy.
IKE, Stuttgart, Federal Republic of Germany.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
The first version of EURLIB was based on EURLIB 1 which was prepared through a joint effort by ESIS at Ispra, Italy, and IKE at Stuttgart, Federal Republic of Germany. This was a coupled neutron, gamma-ray cross-section library with the design goal of sensitivity tests in shielding calculations.
The second version is a library of cross sections for 100-neutron and 20 gamma-ray groups and
was named EURLIB-III. It contains cross sections for 14 materials and is based on ENDF/B-IV data.
5. APPLICATION OF THE DATA
The set of energy limits represents a subset of the energy bounds for the Standard CSEWG Multigroup File. The energy subdivision has been chosen to take into account the adequate representation of the main resonances of the materials involved in the benchmark experiments.
The structure should also permit an acceptable representation of the resonance detector cross
sections commonly used in the various laboratories.
6. SOURCE AND SCOPE OF DATA
It was originally decided to establish a 100 group iron cross section library based on the standard group structure. The basic cross section data should come from ENDF/B3. It was soon decided that, if the standard library was to be useful in the benchmark program, it should not be restricted to the test material only.
The materials included in the library are:
Hydrogen, Carbon, Oxygen, Sodium, Aluminum, Silicon, Calcium, Chromium, Manganese, Iron,
Nickel, Zirconium, Uranium-235, Uranium-238.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS
The data retrieval programs used are DLC2RP and APRFX-I from the DLC-2/100G library.
DLC2RP will retrieve DLC-2G/100G data from a maximum of 46 data sets and merge these data into one data set. The program will then, by input option, edit the data, punch cards in either the ANISN or DTF-IV format, or write an unformatted tape for use by ANISN.
APRFX-I collapses the fine group cross sections to a broad group structure according to a flux
spectrum either input by the user or calculated by the code. The code will average the fine group
cross sections to form either macroscopic or microscopic isotope cross sections and any combination
of macroscopic mixtures of these cross sections on the same problem. It also determines the broad
group input source and generates averaged neutron velocities for use with transport calculations.
8. DATA FORMAT AND COMPUTER
BCD/EBCDIC card images; IBM 360.
9. TYPICAL RUNNING TIME
No study has been made by RSIC of typical running times for EURLIB/EURLIB-III.
Description of DLC-35B/EURLIB-III.
Description of DLC-35A/EURLIB.
DLC-2 Data Retrieval Program Description.
E. Caglioti, G. Hehn, V. Herrnberger, M. Mattes, R. Nicks, and H. Penkuhn, "Generation and
Testing of Shielding Data Libraries for Fission and Fusion Technology," in Fifth International
Conference on Reactor Shielding, Knoxville, Tennessee (April 1977).
11. CONTENTS OF LIBRARY
Included are the referenced documents and one (1.2MB) DOS diskette which contains a neutron
cross section library, a retrieval program, plus output from the sample problem.
12. DATE OF ABSTRACT
KEYWORDS: ANISN FORMAT; BENCHMARK PROBLEM CROSS SECTIONS; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS