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Refining the capture cross sections of103Rh,105Pd,109Ag, and153Eu

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Literature Cited

  1. V. A. Dulin, Perturbation of Critical Reactors and Refinement of Group Constants [in Russian], Atomizdat, Moscow (1979).

    Google Scholar 

  2. Yu. A. Kazanskii, V. A. Dulin, V. P. Zinov'ev, et al., Methods of Studying Reactor Characteristics in BFS Critical Piles [in Russian], Atomizdat, Moscow (1977).

    Google Scholar 

  3. K. Dietze, K. Pährmann, G. Hüttel, and E. Lehmann, “Neutron data check for structural materials by reactivity measurements in a fast facility with energy-independent adjoint flux,” Kernenerg.,29, 401 (1986).

    Google Scholar 

  4. M. M. Savos'kin, I. P. Markelov, M. A. Baryba, et al., “Annotation of KRAB-1 program packet,” Vopr. At. Nauk Tekh., Ser. Fiz. Met. Rasch. Yad. Reakt., No. 6(43), 44 (1984).

    Google Scholar 

  5. L. P. Abagyan, N. O. Bazazyants, M. N. Nikolaev, and A. M. Tsibulya, Group Constants for Reactor and Shielding Calculations [in Russian], Énergoizdat, Moscow (1981).

    Google Scholar 

  6. T. S. Belanova, L. V. Gorbacheva, and O. T. Grudzevich, “Comparative analysis of estimates of the cross sections of radiational neutron capture for the most important fission products,” At. Énerg.,57, No. 4, 243 (1984).

    Google Scholar 

  7. A. V. Ignatyuk, I. V. Kravchenko, and G. N. Manturov, “Library of recomended approximate neutron cross sections for the most important nuclear fission products,” Vorp. At. Nauk Tekh., Ser. Yad. Konst., No. 1, 3 (1987).

    Google Scholar 

  8. A. I. Blokhin, A. V. Ignatyuk, V. N. Koshcheev, et al., “Library of approximate neutrondata files,” in: Neutron Physics. Proceedings of an International Conference on Neutron Physics, Kiev, 21–25 September, 1987 [in Russian], Vol. 1, TsNIIatominform, Moscow (1988), p. 45.

    Google Scholar 

  9. V. V. Sinitsa, “Program for calculating group constants on the basis of libraries of approximate neutron data,” Vorp. At. Nauk Tekh., Ser. Yad. Konst., No. 5(59), 34 (1984).

    Google Scholar 

  10. H. Klippel and J. Smith, The Coupled Fast-Thermal Critical Facility STEK, RCN-209 (1974).

  11. J. Veenema and A. Janssen, Small Sample Reactivity Worths of Fission Product Isotopes and Some Other Materials Measured in STEK, ECN-10 (1976).

  12. T. Anderson, Integral Measurements of Fission Product Reactivity Worths in Some Fast Reactor Spectra, AE-428 (1971).

  13. L. Martin-Deidier, Mesure Integrale de la Capture des Produits de Fission dans les Reacteurs a Neutrons Rapides, CEA-R-5023 (1979).

  14. Y. Harker and R. Anderl, “Integral cross section measurements on fission product nuclides in fast neutron fields,” in: Proceedings of Special Meeting on Neutron Cross Sections of Fission Product Nuclei, Bologna, Italy (1979), p. 5.

  15. M. V. Bokhovko, L. E. Kazakov, V. N. Kononov, et al., “Experimental cross sections of radiational neutron capture in silver in the energy range 4–400 keV,” Vorp. At Nauk Tekh., Ser. Yad. Konst., No. 2, 21 (1987).

    Google Scholar 

  16. R. Macklin and P. Young, Nucl. Sci. Eng.,95, 189 (1978).

    Google Scholar 

  17. R. Macklin and R. Winters, Nucl. Sci. Eng.,78, 110 (1981).

    Google Scholar 

  18. R. Macklin, R. Winters, and J. Halperin, “Recent capture cross section data from ORELA above 2.6 keV,” in: Proceedings of Special Meeting on Neutron Cross Sections of Fission Product Nuclei, Bologna, Italy (1979), p. 103.

  19. W. Poenita, “Fast neutron capture cross section measurements, evaluations, and model calculations of fission product nuclei,” in: Proceedings of Special Meeting on Neutron Cross Sections of Fission Product Nuclei, Bologna, Italy (1979), p. 85.

  20. S. Joly et al., Nucl. Sci. Eng.,70, 53 (1979).

    Google Scholar 

  21. G. Reffo et al., Nucl. Sci. Eng.,80, 630 (1982).

    Google Scholar 

  22. E. Cornelis, “Average capture cross section of fission product nuclei104–106–108–110Pd,” in: Proceedings of an International Conference on Nuclear Data for Science and Technology, Antwerp, Holland (1982), p. 222.

  23. M. Mizumoto et al., “Neutron radiative capture and transmission measurement of107Ag and109Ag,” in: Proceedings of an International Conference on Nuclear Data for Science and Technology, Antwerp (1982), p. 226.

  24. W. Poenitz, “Fast neutron capture cross section measurement with ANL LIST,” in: Proceedings of Special Meeting on Fast Neutron Capture, Argonne, US (1982), p. 111.

  25. Nucl. Sci. Eng.,82, 400 (1982).

  26. M. Mizumoto et al., J. Nucl. Sci. Tech.,16, 711 (1979).

    Google Scholar 

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Authors
  1. S. M. Bednyakov
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  2. M. V. Bokhovko
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  3. G. N. Manturov
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  4. K. Dietze
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Additional information

Central Institute of Nuclear Research, East Germany. Translated from Atomnaya Énergiya, Vol. 67, No. 3, pp. 199–204, September, 1989.

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Bednyakov, S.M., Bokhovko, M.V., Manturov, G.N. et al. Refining the capture cross sections of103Rh,105Pd,109Ag, and153Eu. At Energy 67, 675–682 (1989). https://doi.org/10.1007/BF01123209

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  • DOI: https://doi.org/10.1007/BF01123209

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