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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
1

A measurement of the neutron diffusion parameters of water at different temperatures by the pulsed method

McClure, John Arthur January 1962 (has links)
The neutron diffusion parameters of water and ice were measured by the pulsed source method at two temperatures; 1.0°C. and -19°C. Neutron pulses were obtained at one millisecond intervals by modulating the beam in a Cockcroft-Walton type accelerator. The ₁H³(d,n)₂He⁴ reaction was used to generate neutrons. The samples were contained in cylindrical aluminum cans covered with cadmium. The experiment was conducted inside a large paraffin block which served as a neutron shield and thermal insulator. The temperature of the samples was maintained constant to within ±1°C. Neutrons leaving one surface of the sample were counted in a BF₃ proportional counter. The time distribution of these neutrons was recorded by an eighteen channel time analyzer. The width of each channel was 20 microseconds. The opening of the first channel was delayed 100 microseconds with respect to the start of the neutron burst to minimize harmonics in the neutron decay. A geometric buckling was calculated for each sized sample from B²=[2.405/(R+∈)]²+[π/(H+∈)]² where B² = geometric buckling 2.405 = first zero of J<sub>o</sub> Bessel Functions R = radios of cylinder H = height of cylinder ∈ = extrapolation distance The extrapolation distance ∈ was calculated from ∈ =0.71 λ<sub>tr</sub> where λ<sub>tr</sub> = mean free path of neutrons in water The extrapolation distance was assumed to vary as T<sup>½</sup> where T is the temperature in degrees Kelvin. The measured decay constants, α, were fitted by the method of least squares to a polynomial in B² of the form α = (∑<sub>a</sub>v) ÷ D<sub>o</sub>B² - CB⁴ where ∑<sub>a</sub> = the macroscopic absorption cross-section v = the neutron velocity D<sub>o</sub> = diffusion coefficient C = diffusion cooling coefficient The resultant values of (∑<sub>a</sub>v) and D<sub>o</sub> for each temperature are below. The data did not permit a determination of C. 1.0°C. (∑<sub>a</sub>v) = 4595 ± 365 sec⁻¹ D<sub>o</sub> = 29600 ± 840 cm²/sec -19°C. (∑<sub>a</sub>v) = 4355 ± 263 sec⁻¹ D<sub>o</sub> = 27050 ± 630 cm²/sec / Ph. D.

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