
doi: 10.2172/4789717
Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor. Dose rates and fluxes were found to be extremely low. A comparison was made by means of threshold foil techniques between the fast-neutron flux in a beam hole of the reactor during steady-state operation at 1 kw and during a nominal 250 Mw, 30 msec pulse produced by rapid insertion of approximates two dollars of excess reactivity. The flux over the duration of the pulse was approximately four times that for steady-state operation for 1 hr at 1 kw. Fast-neutron dose rates and thermal-neutron fluxes were measured at each of the four beam ports of the reactor at operating powers of 0, 1, and 5 watts. Some gamma dose rate data was also obtained at 0 and 1 watt. The threshold foil technique used is described. (auth)
Reactor Technology, Zirconium Hydrides, 570, Gamma Radiation, Foils, Radiation Doses, Neutron Flux, Reactivity, Threshold Detectors, Activation, Variations, 530, Fast Neutrons, Measured Values, Neutron Beams, Shielding, Radiation Detectors, Research Reactors, Pulses, Thermal Neutrons, Operation
Reactor Technology, Zirconium Hydrides, 570, Gamma Radiation, Foils, Radiation Doses, Neutron Flux, Reactivity, Threshold Detectors, Activation, Variations, 530, Fast Neutrons, Measured Values, Neutron Beams, Shielding, Radiation Detectors, Research Reactors, Pulses, Thermal Neutrons, Operation
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