Measurements of neutron capture in U²³⁸ in lattices of uranium rods in heavy water

"NYO-9659."Also issued as a Ph. D. thesis in the Dept. of Nuclear Engineering, 1962Includes bibliographical references (pages 119-145)Contract AT(30-1)-234

The measurement of reactor parameters in slightly enriched uranium, heavy water moderated miniature lattices

"MIT-2344-8."U.S. Atomic Energy Commission AT(30-1)234

Heavy Water Lattice Project final report

MIT-2344-12AEC Research and Development ReportBibliography: leaves 181-192U.S. Atomic Energy Commission contract AT(30-1)234

Studies of two-region subcritical uranium heavy water lattices

"February 1969.""MIT-2344-13."Some technical reports have the series numbering of MITNE-84Substantially the same as J.W. Gosnell's Ph. D. thesis in the Dept. of Nuclear Engineering, 1969Includes bibliographical references (leaves [212]-215)Reactor physics parameters were measured in eleven two-region subcritical assemblies moderated by heavy water. The regions of the assemblies consisted of nine different lattices of various fuel rod size, U235 enrichment, and spacing. The following parameters were measured in the assemblies: bare and cadmium-covered gold foil radial traverses; bare gold foil axial traverses; the ratio of epicadmium to subcadmium capture r tes in U238 (P28); and the ratio of fissions in U238 to fissions in U233(628)- From analysis of axial traverses at various radial positions, it was determined that the axial buckling was independent of radial position in the assemblies. A method was developed to apply the age equation to the experimental gold foil traverses. This analysis yielded the quantity [ ... ] for each region of the assemblies. Calculated values of [ ... ] were used to obtain values of the infinite multiplication factor from this parameter.For assemblies of sufficiently large inner regions, the values of km so found agreed within experimental uncertainty with independent determinations. The slowing-down spectra. arising from the age theory analysis were used to extrapolate two-region assembly measurements of P28 to critical assembly values. General agreement was found between these extrapolated values and the results of measurements made in full, single region lattices. The heterogeneous expressions for uncollided flux derived by Pilat were extended to two-region assemblies and used to determine single rod values of 628 from two-region assembly measurements. The theory was also used to predict values of 628 for each of the lattices composing the two-region assemblies. Both the single rod values and the full lattice predictions agreed within experimental error with previously reported results. The determination of material buckling from two-region subcritical assemblies is also discussed.!Because of the nature of the assemblies investigated, satisfactory measurements of the material buckling could not be made.U.S. Atomic Energy Commission contract AT(30-1)-234

Pulsed neutron source

Also issued as an Sc. D. thesis, Massachusetts Institute of Technology. Dept. of Nuclear Engineering, 1967"MIT-2344-7."U.S. Atomic Energy Commission contract AT (30-1)234

Design of a cold neutron source for the MIT reactor

Also issued as a Sc. D. thesis in the Dept. of Nuclear Engineering, MIT, 1970Includes bibliographical references (leaves 211-212

Measurement of gamma-ray spectra from thermal-neutron capture

"AFCRL-63-341."Originally presented as the first author's Ph. D. thesis, Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963Scientific report no. 1 for Contract no. AF19(604)-7492Project 4608; Task 46080

Measurements of the material bucklings of lattices of natural uranium rods in D₂O

"NYO-9660.""AEC Research and development report UC-34 physics (TID-4500, 16th edition)."Originally issued as the first author's Ph. D. thesis, Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962U.S. Atomic Energy Commission AT(30-1)234

The reactor physics of the Massachusetts Institute of Technology reactor redesign

"August, 1970."Also written as a Ph. D. thesis by the first author and supervised by the second and third author, MIT, Dept. of Nuclear Engineering, 1970Includes bibliographical references (pages 284-289)An H20 cooled compact MITR-II core, reflected by D20 has been designed for the MITR to increase the reflector thermal neutron flux at tips of beam ports by a factor of 3 or better, without changing the operating power level of the reactor. The diffusion approximation to the neutron transport equation has been used. A three neutron energy group scheme, that retains essential spatial effects, used in the studies has yielded satisfactory agreement with measured data. The factors which affect the intensity as well as the quality of the reflector thermal neutron flux have been studied. These studies show that the permanent features of the MITR limit the maximum power densities in the MITR-II core to factors between 4.5 and 12 below the corresponding values in reactors employing a similar core concept Nevertheless, the predicted unperturbed reflector thermal neutron flux of 1.lXlO14 n/cm 2-sec in MITR-II yields a reflector flux per unit power that is competitive with the corresponding values available in reactors of its type and a factor of 5.0 higher than that in MITR-I

A study of the fast fission effect in lattices of uranium rods in heavy water

NYO-9661Includes bibliographical references (p. 168-171)AT (30-1) 234