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The ß-half-life of Pu241.
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Results of relative measurements of photofission yields and cross-sections for 233,235U, 237Np, 239,241Pu and 241Am nuclei in the 5-11 MeV region.
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Total cross section and diffusion parameters of benzene
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Nuclear fission and neutron-induced fission cross-sections.
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Resonance production and inclusive cross-sections in dual models
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Theory of neutron resonance cross sections for safety applications.
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Average group data for 241Pu in the 0.1 - 21.5 keV energy region.
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An estimate of the total cross section of accumulated fission products.
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Curves and tables of neutron cross sections of fission product nuclei in Jendl-3.
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Curves and tables of neutron cross sections of fission product nuclei in JENDL-3.
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Evaluation of nuclear data of 244Pu and 237Pu.
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Method for analytical calculation of group-averaged functionals of neutron cross-sections in the unresolved resonance region.
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Consistent calculations of fast neutron induced fission, [n,2n] and [n,3n] cross-sections for 71 isotopes of Th, Pa, U, Np, Pu, Am, Cm, Bk and Cf.
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Neutron activation resonance integal of 74 Ge and 76 Ge and evaluation of the keV neutron radiative capture cross section and resonance integral
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Anomalous 96Zr resonance integral to thermal activation cross-section ratio and the neutrón activation resonance integral of 94Zr and 96Zr
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Discriminación por forma de pulso aplicada a detectores para medición de la carga pulmonar de Pu-239 y Am-241
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Thermal neutron cross sections and diffusion parameters of diphenyl and dowtherm-A using a synthetic scattering function
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Evaluation of neutron cross-sections for fission product nuclei in the energy range up to 50 MeV.
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The preparation and properties of Pu242.
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Comparison of double-differential neutron emission cross sections calculated from evaluated nuclear data libraries with experimental data.
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Comparison of double-differential neutron emission cross sections calculated from evaluated nuclear data libraries with experimental data.
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Determination of neutron resonance parameters with the IBR-30 pulsed neutron source for U-238 and Sm isotopes.
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Neutron-photon multigroup cross sections for neutron energies up to 400 mev : HILO86R -Revision of HILO86 library-.
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Neutron cross sections and technology; proceedings of a conference.