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        The Measurement of Neutron Activation Cross Section of ^(59)Co Below 36 MeV

        E. Simeckov,P. Bem,V. Burjan,M. Gotz,M. Honusek,V. Kroha,J. Novak,U. Fischer,S. P. Simakov,R. A. Forrest 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23

        An accurate knowledge of the cross section for neutron-induced reactions on ^(59)Co is of importance due to use of cobalt as a structural material in fission and fusion reactors, its applicability in neutron dosimetry and for testing theoretical models as well. The thin Co foils (0.25 mm thickness, 99.9% purity, Goodfellow product) were irradiated in the quasi-momoenergetic p-Li neutron field. For the production of the neutron fields, the proton beam from the NPI energy-variable cyclotron U120M at proton energies 19.8, 25.1, 27.6, 30.1, 32.7, 35.0, and 37.4 MeV and thin ^7Li target with carbon stopper were used. The reaction ^7Li(p,n) produces the high-energy quasi-monoenergetic neutrons with tail to lower energies. The flux density and neutron spectra were evaluated by MCNPX code using ^7Li(p,n) cross section measurement of other authors and including correction to the NPI target layout. The time profile of the neutron source strength during the irradiation was monitored by the proton beam current on the neutron-source target, recorded by a calibrated current-to-frequency converter on a PC. Au foils were used as additional monitors. The foil activity determination was performed by the nuclear spectrometry method employing two calibrated HPGe detectors of 23 and 50% efficiency and of FWHM (Full Width Half Maximum) 1.8 keV at 1.3 MeV for gamma-ray measurement. The reaction rates for ^(59)Co(n,p)^(59)Fe, ^(59)Co(n,α)^(56)Mn, ^(59)Co(n,2nα)^(54)Mn, ^(59)Co(n,3n)^(57)Co, ^(59)Co(n,2n)^(58m)Co, and ^(59)Co(n,2n)^(58g)Co were obtained. Integral activation cross sections were estimated. The preliminary results are discussed.

      • KCI등재

        Analysis of the Dosimetry Cross Sections Measurements up to 35 MeV with a ^7Li(p,xn) Quasi-Monoenergetic Neutron Source

        S. P. Simakov,U. Fischer,Pavel Bem,V. Burjan,M. Gotz,M. Honusek,V. Kroha,J. Novak,E. Simeckova,R. A. Forrest 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23

        To improve the status of the dosimetry reaction data above 20 MeV, the activation cross sections on Bi, Au, Co and Nb have been measured at the NPI/Rez cyclotron facility with a quasi-monoenergetic p-^7Li neutron source. The present work comprises the computational analysis of this experiment. It includes the Monte-Carlo simulation of the experimental set-up with the MCNPX code and relevant cross section data for proton and neutron induced reactions to predict the energy differential neutron flux in the irradiated foils. This approach has been validated against p-Li neutron spectra measured by different techniques. By making use of the modified unfolding code SAND-II, the dosimetry cross sections have been derived from the detected γ-ray activities. This has brought the new experimental results in the neutron energy domain between 18 and 35 MeV with estimated uncertainty at the level of 10%. They were used for validation of the activation (EAF, IEAF, IRDF) and the general purpose (ENDF) cross section files.

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