IAEA1407 ZZ-RRDF-98.

1. NAME OR DESIGNATION:  ZZ-RRDF-98.

3. DESCRIPTION OF PROGRAM OR FUNCTION

  
FORMAT: ENDF-6 format
  
NUMBER OF GROUPS: Continuous energy
  
DOSIMETRY REACTIONS: 6-C-12(n,2n), 8-O-16(n,2n), 9-F-19(n,2n), 12-Mg-24(n,p), 22-Ti-46(n,2n), 22-Ti-46(n,p), 22-Ti-47(n,x), 22-Ti-48(n,p), 22-Ti-48(n,x), 22-Ti-49(n,x), 23-V-51(n,alpha), 26-Fe-54(n,2n), 26-Fe-54(n,alpha), 26-Fe-56(n,p), 27-Co-59(n,alpha), 29-Cu-63(n,alpha), 33-As-75(n,2n), 41-Nb-93(n,2n), 41-Nb-93(n,n'), 45-Rh-103(n,n'), 49-In-115(n,n'), 59-Pr-141(n,2n),
  
ORIGIN: Russian Federation
  
WEIGHTING SPECTRUM: None
  
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RRDF-98 contains original evaluations of cross section data performed at the Institute of Physics and Power Engineering, Obninsk, for 22 neutron induced dosimetry reactions.
The dataset also contains the corresponding covariance matrices.

4. METHODS

The evaluation of excitation functions was performed on the basis of statistical analysis of corrected experimental data in the framework of generalized least squares method and taking into account the results of optical-statistical STAPRE and GNASH calculations. The experimental cross section data including the most recent results were critically reviewed and processed in this study. If necessary, the data were normalized in order to make adjustments in relevant cross sections and decay schemes.
  
The covariance matrices were prepared and the evaluated cross section data are presented in ENDF-6 format (Files 3, 33). For estimation of correlations between experimental data the total uncertainties of measured cross sections have been separated into statistical and systematic parts and correlation coefficients between components of systematic parts were assigned according to information given in the original publications and EXFOR library. Then the correlation matrix of cross sections measured within one experiment was calculated and approximated by matrix with a constant (average) correlation coefficient. The overall correlation matrix was composed of such submatricies in the assumption that the cross sections measured in different experiments do not correlate with each other. It should be noted that such procedure of the statistical analyses guarantees positive definiteness of the covariance matrices of evaluated cross sections.

8. RELATED OR AUXILIARY PROGRAMS:  STAPRE and GNASH.

10. REFERENCES

1. S.A.Badikov et al., Proc. of Specialists Meeting on Evaluation and Processing of Covariance Data, Oak Ridge, USA, October 7-9, 1992, M.Wagner, Ed., OECD, Paris, 1993, p.105.
  
2. H.Wienke,Ed. Update to Nuclear Data Standards for Nuclear Measurements. Report INDC(NDS)- 368, IAEA, Vienna, May 1997
  
3. W.Mannhart, Report IAEA-TECDOC-410, IAEA, Vienna, 1987, p.158.
  
4. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. Apr. 1989
  
5. N.P.Kocherov and P.K.McLaughlin. The International Reactor Dosimetry File (IRDF-90 Version 2), Report IAEA-NDS-141, Rev.3, March 1996, Vienna.

6. W.Mannhart, Handbook on Nuclear Activation Data. IAEA Technical Report. Series No.273, IAEA,Vienna, 1987, p.413; W.Mannhart, Proc.5-th ASTM-EURATOM Symposium on Reactor Dosimetry, Geesthacht, Sept. 24-28, 1984, v.2, p.813.
  
7. F.Nasyrov, B.D.Sciborsky, Atomnaya Energiya, Vol. 25 ,1968, p. 437.
  
8. K.Kobayashi, T.Kobayashi, Progress Report NEANDC(J)

155/U ,1990, p.52.
  
9. D.M.Gilliam et al., Proc. 5-th ASTM-EUARATOM. Symposium on Reactor Dosimetry, Geesthaft, Sept. 24-28, 1984, v.2, p.867.

- K.I. Zolotarev, A.V. Ignatyuk, V.N. Mahokhin, A.B. Pashchenko:
RRDF-98, Russian Reactor Dosimetry File
IAEA-NDS-193, Rev. 0  (March 1999)

Tested at the NEA DB on a PC INTEL Pentium-IV 3GHz 512Mbytes.

Tested at the NEA DB on WINDOWS XP Professional.

15. NAME AND ESTABLISHMENT OF AUTHORS

K.I. Zolotarev, A.V. Ignatyuk, V.N. Mahokhin, A.B. Pashchenko
Institute of Physics and Power Engineering
P.O. Box 249020, Obninsk, Kaluga Reg.
Russia

nds-193.htm  Table of data for the isotopes/reactions and figures
nds-193.pdf   IAEA-NDS-193 document
R-IRDF.doc  Content of RRDF-98 compared to IRDF-90
RRDF.txt    Table of nuclide materials and reactions
SPISOK.doc   Comments file for RRDF-98 (1 451)
RRDF98.dat   Complete ENDF format RRDF-98 library
NDS-Dat\  Data files
NDS-Fig\   Figures