1. NAME AND TITLE OF DATA LIBRARY
IRDF-82: International Reactor Dosimetry Data.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM
No retrieval program is included in the package.
International Atomic Energy Agency, Vienna, Austria.
4. HISTORICAL BACKGROUND AND INFORMATION
IRDF-82 is an international reactor dosimetry data package. A retrieval code is provided for
accessing the reaction cross sections.
5. APPLICATION OF THE DATA
IRDF-82 contains 620 neutron group cross sections (SAND-II format) based on the ENDF/B-V
Special Purpose Dosimetry File as well as other reaction cross sections important for dosimetry
applications. In addition, multigroup spectra for ten reference benchmarks are also provided.
6. SOURCE AND SCOPE OF DATA
This 1982 version of the International Reactor Dosimetry File is composed of two different parts.
The first part is made up of a collection of dosimetry cross sections and the second part contains a
collection of benchmark spectra. For ease of use in dosimetry applications, both cross sections and
spectra are distributed in multigroup (as opposed to continuous energy) form. Each of these two parts
can be found in the ENDF/B-V format as a separate computer file.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
EBCDIC card images; IBM 360/370.
9. TYPICAL RUNNING TIME
D. E. Cullen, N. Kocherov, and P. M. McLaughlin, "The International Reactor Dosimetry File
(IRDF-82)," IAEA-NDS-41/R (January 1982).
11. CONTENTS OF LIBRARY
Included are the referenced document and one (1.2MB) DOS diskette which contains the
international reactor dosimetry files NDS and spectra, the merger source program, merged cross
sections, and merger JCL and data, plus printed output from sample problem.
12. DATE OF ABSTRACT