1. NAME AND TITLE
ACTV-FUS/INT: International Library of Neutron Activation Cross-Section Data for
Fusion Reactor Application.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
None is provided with the package. However, the PSR-333/CHENDF 6.8 package can
be used to access the data.
International Atomic Energy Agency, Vienna, Austria.
4. HISTORICAL BACKGROUND AND INFORMATION
At the May 1989 FENDL meeting, the Working Group on Neutron Activation Data initiated an intercomparison of activation cross sections important for fusion reactor technology. It was agreed that national nuclear data centers will send to the IAEA/Nuclear Data Section their contributions, according to a list of reactions selected on the basis of inventory calculations.
A list of 256 important reactions that are significant in producing activation both at short and long cooling times has been compiled by R. Forrest at Harwell Laboratory, UKAEA. The list was distributed to all interested parties and now many activation data files have been received at the NDS from institutes participating in this exercise. Very detailed graphical intercomparisons have been prepared at the NDS, plotting, for each reaction, overlays of the various submitted evaluated data sets and experimental data from EXFOR.
This review and intercomparison activity has the practical goal of creating the activation
data sublibrary of FENDL. Selection of the 256 specific evaluations which constitutes the first
version of the activation cross-section sublibrary was made at the June 1990 FENDL meeting. This
list of evaluations, with a few subsequent modifications, was the basis of the first version of the
International Activation Cross-Section Data Library for neutron reactions, most important for
activation in fusion reactor technology (as a sublibrary of FENDL). At the next FENDL meeting,
the review and selection process was to be renewed leading to the creation of a second version.
5. APPLICATION OF THE DATA
This library is used for calculation of activation in fusion reactor technology.
6. SOURCE AND SCOPE OF DATA
The library contains cross-section data for 372 neutron induced activation reactions of 150
isotopes for incident neutron energies up to 20 MeV. The evaluated data were taken from REAC-2, REAC-ECN-5, BOSPOR-86, SINCROSACT, ADL-90, ENDF/B-VI, JENDL3 and BROND
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS
No retrieval program is included, however the CHECKR utility of CHENDF 6.8 was used
to check ACTIV87 at RSIC, and the files do not consistently conform to ENDF formats.
8. DATA FORMAT and COMPUTER
ENDF-6 format; card images.
9. TYPICAL RUNNING TIME
A. B. Pashchenko, "ACTV-FUS/INT The International Library of Neutron Activation
Cross-Section Data for Fusion Reactor Application (FENDL Activation Sublibrary)" (November
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and library on one tape cartridge in TAR format.
12. DATE OF ABSTRACT
KEYWORDS: EVALUATED NEUTRON CROSS SECTIONS; REACTION CROSS SECTIONS