RSICC DATA PACKAGE DLC-199

1. NAME AND TITLE OF DATA LIBRARY

EAF-99: European Activation File - 99.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

None included.

3. CONTRIBUTOR

EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon Oxfordshire, United Kingdom.

4. HISTORICAL BACKGROUND AND INFORMATION

In the European fusion programme, safety and environmental issues are of great importance in the continuing development of power plants. In support of this programme, a sound, complete and reliable neutron cross section data library is required. The European Activation File (EAF) project has been an ongoing process performed through European and world-wide co-operation that has led to the creation of succeeding EAF versions. The latest release, EAF-99, has benefitted from the generation and maintenance of comprehensive activation files and the maturing of the processing code SYMPAL. Cross-section validation exercises against both experimental data or systematics, started on the EAF-4 files and enable a comprehensive assessment of the data. Using SYMPAL, 3,168 reactions and branching ratios were systematically normalized to either experimental or systematic data. These are challenging tasks when the source contains threshold reactions with an energy dependent branching ratio. Although EAF-99 is the best-validated cross section library in the world, less than 16% of all EAF-99 reactions can currently be compared with experimental information, and sometimes only for very limited energy ranges that are not always relevant.

Recently, for the first time, results of integral experiments have been used to adjust data. Validation of activation code predictions, and thereby of cross section and decay data, has been performed by means of direct comparison with measurements of sample structural material under fusion-relevant neutron spectra. Irradiations have been carried out at ENEA FNG, FZK Isochron-cyclotron, Sergiev Posad SNEG-13 and JAERI FNS and integral C/E comparisons made. The results of these benchmarking exercises have triggered, when correlated with other sources of information, corrective measures to be taken on a selection of important reactions.

5. APPLICATION OF THE DATA

The pointwise and groupwise nuclear data libraries and uncertainty data library included in this distribution were developed for use with the inventory code FISPACT. Note that the RSICC package is a subset of the complete EAF-99 library. See the UKAEA web site for more information on the EASY-99 code system which includes EAF-99 data: http://www.fusion.org.uk. RSICC distributes EAF-97 libraries within the CCC-678/EASY-97 code package.

6. SOURCE AND SCOPE OF DATA

The EAF-99 library contains 12,468 excitation functions involving 766 different targets from 1H to 257Fm, atomic numbers 1 to 100, in the energy range 10-5 eV to 20 MeV. The 1,500,000 lines that make up the pointwise file are then processed into numerous groupwise files with different micro-flux weighting spectra to meet various user needs. Uniquely, an uncertainty file is also provided that quantifies the degree of confidence placed on the data for each reaction channel. All reaction channels that have been validated either through cross-section plots or integral experiment results have been updated.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

ASCII data and PDF documentation; Many computers (D00199MNYCP00).

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

J-Ch. Sublet, J. Kopecky, and R. A. Forrest, "The European Activation File: EAF-99 Cross Section Library," UKAEA FUS 408 (December 1998) (hardcopy and electronic PDF).

J-Ch. Sublet, J. Kopecky, R. A. Forrest, "EAF-99 Report File," EDS-3a (electronic PDF only).

J-Ch. Sublet, J. Kopecky, and R. A. Forrest, "EAF-99/README" (January 29, 1999)(electronic PDF only).

11. CONTENTS OF LIBRARY

Included are the referenced documents and one CD-ROM which contains the EAF-99 data and PDF documentation in both a compressed Unix tar file and a self-extracting compressed DOS file.

12. DATE OF ABSTRACT

October 1999.

KEYWORDS: FUSION NEUTRONICS; MULTIGROUP CROSS SECTIONS; DOSIMETRY CROSS SECTIONS; REACTION CROSS SECTIONS