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AbstractAbstract
[en] A Monte Carlo analysis of a time-dependent neutron and secondary gamma-ray integral experiment on a thick concrete and steel shield is presented. The energy range covered in the analysis is 15-2 MeV for neutron source energies. The multigroup MORSE code was used with the VITAMIN C 171-36 neutron-gamma-ray cross-section data set. Both neutron and gamma-ray count rates and unfolded energy spectra are presented and compared, with good general agreement, with experimental results
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Nov 1981; 29 p; Available from NTIS., PC A03/MF A01
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Report
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Numerical Data
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COMPUTER CALCULATIONS, CONCRETES, CROSS SECTIONS, EXPERIMENTAL DATA, GAMMA SPECTRA, GAMMA TRANSPORT THEORY, GROUP CONSTANTS, MEV RANGE 01-10, MEV RANGE 10-100, MONTE CARLO METHOD, MULTIGROUP THEORY, NEUTRON SPECTRA, NEUTRON TRANSPORT, NEUTRON TRANSPORT THEORY, PHOTON TRANSPORT, SHIELDING, STEELS, THEORETICAL DATA
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