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Showing 1 to 8 of 8 for “"neutron cross sections"”.

  1. Integral Tests of Neutron Cross-Sections for Iron, Niobium, Beryllium, and Polyethylene

    Made available in DSpace on 2014-12-14T06:25:56Z (GMT). No. of bitstreams: 1 7606811.pdf: 4558159 bytes, checksum: 6c299ad58c68afc9e3d74f9ef4e2b1f5 (MD5) Previous issue date: 1975

    uiuc Repository record for Integral Tests of Neutron Cross-Sections for Iron, Niobium, Beryllium, and Polyethylene (opens in a new tab)

  2. Integral Testing of Neutron Cross-Sections Using Simultaneous Neutron Andgamma-Ray Measurements

    Made available in DSpace on 2014-12-14T06:26:03Z (GMT). No. of bitstreams: 1 7714964.pdf: 3164131 bytes, checksum: 9a67f4994acfcb539c21b5d529b4bc5d (MD5) Previous issue date: 1977

    uiuc Repository record for Integral Testing of Neutron Cross-Sections Using Simultaneous Neutron Andgamma-Ray Measurements (opens in a new tab)

  3. Study of the Bi209 (gamma,pi-xn) Po209-x and Pb206 (He3,xn) Po209-x reactions by detection of polonium alpha activities

    The cross sections for Bi 209{gamma, pi-xn ) Po209-x were measured for x = 0-3, 5, and 7 and used to estimate the total (gamma, pi-) cross section. Total (gamma, pi-) cross sections have not previously been measured for a complex nucleus. At bremsstrahlung energies of 200,220, and 250 MeV, the …

    uiuc Repository record for Study of the Bi209 (gamma,pi-xn) Po209-x and Pb206 (He3,xn) Po209-x reactions by detection of polonium alpha activities (opens in a new tab)

  4. Computer simulation of neutron capture therapy.

    … computer the production and use of reactor neutron beams f or boron capture therapy of brain tumors. The simulation accounts for radiation dose distributions in tissue produced by fast neutrons and by neutron capture reaction products such as gamma rays, C -particles, protons, and heavy …

    mit Repository record for Computer simulation of neutron capture therapy. (opens in a new tab)

  5. A lattice boltzmann/s n framework for coupled heat transfer and neutron transport problems

    … dissertation is to study the coupling between neutron transport and heat conduction equations with temperature-dependent thermal conductivity and temperature-dependent neutron cross sections. The neutron transport equation is solved using the discrete ordinates method (SN ); and the heat …

    uiuc Repository record for A lattice boltzmann/s n framework for coupled heat transfer and neutron transport problems (opens in a new tab)

  6. Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico

    … compiled for this work. The EVENT (EVEn parity Neutron Transport) radiation transport code was chosen to analyze and verify the steady-state and time-dependent experimental configurations on the AGN. Complex AGN models were developed to test the EVENT code and the case-dependent multigroup …

    unm Repository record for Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico (opens in a new tab)

  7. Measurement of neutron production from an ¹⁸O target for the production of radioactive-ion beams at iThemba LABS

    … proton beams from a cyclotron. However, neutron-induced fission gives enhanced production of neutron-rich fission fragments compared to proton-induced fission, thus there is a need to find efficient ways of producing neutrons from protons. Beryllium targets have been suggested, but …

    cape-town Repository record for Measurement of neutron production from an ¹⁸O target for the production of radioactive-ion beams at iThemba LABS (opens in a new tab)