International reactor dosimetry file 2002 (IRDF-2002).
Contributors: International Atomic Energy Agency.
Series: Technical reports series -- no. 452.; Technical reports series (International Atomic Energy Agency) -- no. 452.
Publisher: International Atomic Energy Agency
Published: 2006
Place of publication: Vienna
Language: eng
Number of pages: 147
ISBN-13: 9789201051066
Subjects: Neutrons -- Measurement.; Neutron cross sections -- Measurement.; Radiation dosimetry.
Other titles: IRDF-2002.
Description: An updated, tested and standardized reactor dosimetry cross-section database with associated uncertainty data and relevant decay data has been assembled to create a new data library for use in assessments of the service life of reactor pressure vessels. The resulting IRDF-2002 data library is available on CD-ROM and through the Internet, and the selection procedure and contents are described in this publication. This set of recommended high-quality data is also appropriate for use in other neutron metrology applications, such as boron neutron capture therapy, therapeutic use of radioisotopes, nuclear physics measurements and reactor safety studies.--Publisher's description.
Notes: Includes bibliographical references.

Available both in print and online.
Table of contents: title: Introduction / R. Paviotti-Corcuera and E.M. Zsolnay; title: New Russian evaluations for IRDF-2002 / K.I. Zolotarev; title: Selection of candidate cross-sections for IRDF-2002 / E.M. Zsolnay and H.J. Nolthenius; title: Response of activation reactions in the neutron field of californium-252 spontaneous fission / W. Mannhart; title: Evaluation of cross-sections at 14 MeV for IRDF-2002 / L.R. Greenwood; title: Final selection of cross-sections for IRDF-2002, and characterization of the selected data / E.M. Zsolnay and H.J. Nolthenius; title: Consistency test of the cross-section data in reference neutron fields / P.J. Griffin; title: Radiation damage files and computer codes / P.J. Griffin and L.R. Greenwood; title: Decay data and isotopic abundances for dosimetry applications / O. Bersillon.