Soviet Atomic Energy

, Volume 69, Issue 1, pp 583–587 | Cite as

Prompt fission-neutron spectra in the reactions of 1.5-MeV neutrons with235U

  • H. MÄrten
  • A. Ruben


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Literature cited

  1. 1.
    H. Knitter, M. Coppola, M. Islam, et al., “Fission neutron energy spectra induced by fast neutrons on238U,235U, and239Pu,” in: Proc. Consult. Meet. of Prompt Fission Neutron Spectra, Vienna, 25–27 August 1972. IAEA, Vienna (1972), pp. 41–57.Google Scholar
  2. 2.
    N. I. Fetisov, S. P. Simakov, A. M. Trufanov, et al., “Physical characteristics of a gas tritium target as a monoenergetic neutron source,” Prib. Tekh. Eksp., No. 6, 22–25 (1980).Google Scholar
  3. 3.
    A. M. Trufanov, V. S. Nesterenko, N. I., Fetisov, et al., “A fast-neutron spectrumeter based on an electrostatic accelerator,” ibid., No. 2, 50–54 (1979).Google Scholar
  4. 4.
    J. Grundl and C. Eisenhauer, “Benchmark neutron fields for reactor dosimetry,” in: Neutron Cross Sections for Reactor Dosimetry, Report IAEA-208, Vienna (1978), Vol. 1, p. 53.Google Scholar
  5. 5.
    L. V. Chulkov, A Program for Calculating the Neutron-Recording Efficiency of a Stilbene Crystal [in Russian], Preprint IAé-2594, Moscow (1976).Google Scholar
  6. 6.
    S. P. Simakov, G. N. Lovchikova, A. M. Trufanov, et al., “Fast-neutron elastic and inelastic scattering cross sections for indium isotopes,” At. énerg.,51, No. 4, 244–247 (1981).Google Scholar
  7. 7.
    V. M. Bychkov, N. V. Kornilov, A. B. Pashchenko, and M. V. Skripova, Reaction Cross Sections Recommended as Standards for Neutron Measurements [in Russian], Preprint FéI-1917, Obninsk (1988).Google Scholar
  8. 8.
    G. N. Lovchikova, A. V. Polyakov, O. A. Sal'nikov, et al., Neutron-Emission Spectra for Thorium-232 and Uranium-235 for an Incident Neutron Energy of 6 MeV [in Russian], Preprint FéI-1564, Obninsk (1984).Google Scholar
  9. 9.
    A. A. Androsenko and P. A. Androsenko, “The BRAND software suite for calculating radiation transport characteristics by Monte Carlo methods,” in: Aspects of Nuclear Science and Engineering, Reactor Physics and Engineering Series [in Russian], Issue 7 (1985). p. 33.Google Scholar
  10. 10.
    H. MÄrten et al., Rep. IAEA INDC (GDR)-18/1, Vienna (1984).Google Scholar
  11. 11.
    Nuclear Standards File INDC/NEUNDC Version: 1980, INDC-36/LN, Vienna (1981).Google Scholar
  12. 12.
    H. MÄrten and D. Seeliger, “Description of the252Cf (sf) neutron spectrum in the framework of a generalized Madland-Nix model,” Nucl. Sci. Eng.,93, 370 (1986).Google Scholar
  13. 13.
    H. MÄrten et al., “On the mechanism of fission neutron emission,” in: Proc. 15th IN-tern. Symp. Nucl. Phys., ZfK-592, Dresden (1986), p. 1.Google Scholar
  14. 14.
    M. Kildir and N. Aras, “Monte Carlo calculation of the deexcitation of fission fragments in the spontaneous fission of252Cf,” Phys. Rev. C,25, 365 (1982).Google Scholar

Copyright information

© Plenum Publishing Corporation 1991

Authors and Affiliations

  • H. MÄrten
    • 1
  • A. Ruben
    • 1
  1. 1.German Democratic Republic

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