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.

3. CONTRIBUTOR

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 libraries.

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

None noted.

10. REFERENCE

A. B. Pashchenko, "ACTV-FUS/INT The International Library of Neutron Activation Cross-Section Data for Fusion Reactor Application (FENDL Activation Sublibrary)" (November 1991).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and library on one tape cartridge in TAR format.

12. DATE OF ABSTRACT

August 1993.