## A method of determining the intermediate energy neutron dose |

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0.6 Mev source a l/E spectrum amount of moderation Assuming l/E Spectrum assumption average energy average relative counting cadmium Count rates obtained counting efficiencies counting rate curves COUNTS FROM FAST counts per minute data taken detection efficiency DETERMINING THE INTERMEDIATE EBR-I ENERGY DOSE RATES ENERGY NEUTRON DOSE energy spectrum experimental counting ratio experimental data Experimental Results Assuming FAST NEUTRON ENERGY fast spectrum fission spectrum fraction of counts fraction of fast fuel plates gamma field gamma sensitivity graph indicated intermediate energy neutron intermediate energy range intermediate range intermediate to fast l/E neutrons l/E spectrum ratios lithium iodide lower energy MTR-ETR n/cm sec neutron detector neutron dose rate neutron flux neutron source Nomograph number of neutrons Po-Be source pure l/E spectrum ratio of intermediate ratios expected ratios obtained relative counting rates Results Assuming l/E RPG l/E shielding spectra technique thermal neutron total count total dose rate values y-axis