The reactor physics of the Massachusetts Institute of Technology reactor redesign
Name
856650210.pdf
Size
18.16 MB
Format
Adobe PDF
Checksum (MD5)
713132e9a0b01d6cc4db22e3f48e3b93
Author(s)
Addae, Andrews Kwasi
Lanning, David D.
Thompson, Theos Jardin, 1918-1970
Date Issued
1970
Publisher
Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970]
Series/Report no.
MITNE ; no. 118
Abstract
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.
Description
"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, 1970
Includes bibliographical references (pages 284-289)
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