Computer Programs

NAME OR DESIGNATION, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS, CPU, FEATURES, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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To submit a request, click below on the link of the version you wish to order. Rules for end-users 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

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

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.

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

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

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.

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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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.

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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IAEA1407/01

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

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IAEA1407/01

nds-193.htm Table of data for the isotopes/reactions and figuresnds-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

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