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IAEA1407 ZZ-RRDF-98.

ZZ RRDF-98, Cross-sections and covariance matrices for 22 neutron induced dosimetry reactions

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1. NAME OR DESIGNATION:  ZZ-RRDF-98.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-RRDF-98 IAEA1407/01 Tested 24-OCT-2005

Machines used:

Package ID Orig. computer Test computer
IAEA1407/01 Many Computers PC Windows
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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.
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS:  STAPRE and GNASH.
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9. STATUS
Package ID Status date Status
IAEA1407/01 24-OCT-2005 Tested at NEADB
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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.
IAEA1407/01, included references:
- 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)
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11. HARDWARE REQUIREMENTS
IAEA1407/01
Tested at the NEA DB on a PC INTEL Pentium-IV 3GHz 512Mbytes.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS
IAEA1407/01
Tested at the NEA DB on WINDOWS XP Professional.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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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
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16. MATERIAL AVAILABLE
IAEA1407/01
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
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17. CATEGORIES
  • Z. Data.

Keywords: activation analysis, covariance matrices, cross sections, foils, neutron flux.