1. NAME AND TITLE OF DATA LIBRARY
IRDF-90: The International Reactor Dosimetry File.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
No retrieval programs are included.
International Atomic Energy Agency, Vienna, Austria.
4. HISTORICAL BACKGROUND AND INFORMATION
The library was created to be used as a data base for reactor neutron dosimetry by the foil activation method and subsequent neutron spectrum unfolding. The library contains 3 files: a set of activation reaction cross-sections, a set of reference neutron spectra, and a set of damage cross-sections.
5. APPLICATION OF THE DATA
The International Reactor Dosimetry File (IRDF-90) contains recommended neutron cross-section data to be used for reactor neutron dosimetry by foil activation. It also contains selected recommended values for radiation damage cross-sections and benchmark neutron spectra. This library supersedes all earlier versions of IRDF.
6. SOURCE AND SCOPE OF DATA
The IRDF-90 version 2 contains 39 neutron dosimetry reaction cross-sections from the latest revisions of the ENDF/B-6, 14 evaluations made by Prof. H. Vonach and his co-workers at the IRK in Vienna and 5 evaluations by the specialists from the Chinese Nuclear Data Center in Beijing, prepared specially for this file under contract with the IAEA. The data in the original ENDF-6 format were processed to 640 group extended SANDII format in the Nuclear Data Section of the IAEA using the processing codes LINEAR, RECENT and GROUPIE by D. E. Cullen. The covariance information is not processed by these codes, and it is contained in IRDF-90 in the original ENDF-6 format.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS
8. DATA FORMAT AND COMPUTER
Card images. The library requires 2.5 MB of hard disk space.
9. TYPICAL RUNNING TIME
Run time depends on the number of iterations in the unfolding procedure and is typically 1-5 minutes on a PC 386.
a. Included in the package:
N. P. Kocherov and P. K. McLaughlin, "The International Reactor Dosimetry File (IRDF-90 Version 2)," IAEA-NDS-141, Rev. 2 (October 1993).
N. P. Kocherov and P. K. McLaughlin, "The International Reactor Dosimetry File (IRDF-90)," IAEA-NDS-141, Rev. 0 (August 1990).
D. E. Cullen and P. K. McLaughlin, "The International Reactor Dosimetry File (IRDF-85),"
IAEA-NDS-11, Rev. 1 (April 1985).
b. Background material:
E. M. Zsolnay and H. J. Nolthenius, "Test of the IRDF-90.V.1 Reactor Dosimetry Library," ECN-91-004 (January 1991).
11. CONTENTS OF PACKAGE
The package contains the references listed above, and the data library, which is transmitted on one DS/HD diskette in self extracting DOS files.
12. DATE OF ABSTRACT
November 1992, January 1994.
KEYWORDS: BASED ON ENDF/B-V; BASED ON ENDF/B-VI; DAMAGE CROSS SECTIONS; DOSIMETRY CROSS SECTIONS; REACTION CROSS SECTIONS; NEUTRON CROSS SECTIONS; RADIATION ENVIRONMENT