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LECTURE NOTES ON REACTOR CONTROLS

Description: This material is the outgrowth of the notes prepared for lectures on reactor controls given in 1953-55 at the Oak Ridge School of Reactor Technology. The course on reactor controls was for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. Topics are discussed on kinetics, neutron energies, poisoning, analog computing, instrumentation, start-up, neutron sources, etc. (W.D.M.)
Date: June 24, 1959
Creator: Walker, C S
Partner: UNT Libraries Government Documents Department

HEAT RELEASE IN NUCLEAR REACTORS

Description: Discussions are included on energy sources and modes of local deposition of heat, fission fragment and BETA decay energy, neutron energy, energy release by BETA decay of activated nuclei, neutron flux distribution, gamma heating calculations, and integration of the gamma heating equation for simple cases. (M.H.R.)
Date: October 1, 1956
Creator: Alexander, L.G.
Partner: UNT Libraries Government Documents Department

HOMOGENEOUS HIGH-FLUX REACTOR

Description: Maximum thermal-neutron fluxes obtainable for the case that maximum power density is limited to 100 w-/cm/sup 3/, and for the case that total reactor power is 100 Mw are listed for a homogeneous reactor, and for five moderators. (auth)
Date: March 31, 1958
Creator: Ergen, W.K.
Partner: UNT Libraries Government Documents Department

Nuclear Instrumentation Source Range Detectors. Core 1, Seed 2. Test Results T-641329

Description: A test was made to determine the effects of excessive neutron flux and humidity on various BF/sub 3/ detectors. Singleelement BF/sub 3/ detectors were installed in channels A, B, and C. A four-element detector was installed in channel D. Two of the four BF/sub 3/ tubes in channel D had their Kovar seals cut in onder to determine the effect of humidity. Of the two single-element BF/sub 3/ detectors installed in channels A and B and subjected to excessive neutron flux levels, the channelA detector failed. The channel-B detector appeared to be operating satisfactorily at the completion of the test. The channel-C detector, operated normally and appeared to be satisfactory at the end of the test. Channel-D detectors appeared to have failed since the final applied voltage curve indicated no high-voltage plateau. (W.L.H.)
Date: October 1, 1960
Partner: UNT Libraries Government Documents Department

Flux Program for the IBM 704

Description: Monitor activation theory leading to the basic relation between the monitor weight and activity and the neutron flux is presented. Manipulations to convent the theory into a form suitable for machine computation and details concerning programing, accuracy, range, usage, and costs are included along with a sample case. (auth)
Date: May 1, 1960
Creator: Haynes, V. O. & Williams, B. D.
Partner: UNT Libraries Government Documents Department

EXPERIMENTAL DETERMINATION OF CORRECTIONS TO THE NEUTRON ACTIVATION OF GOLD FOILS EXPOSED IN WATER

Description: The corrections required to deduce unperturbed neutron fluxes from measurements with foil absorbers were determined experimentally for the case of gold foils exposed in a light-water medium. The results are in good agreement with the theoretical predictions of Dalton and Osborn and of Ritchie and Eldridge. (auth)
Date: April 1, 1963
Creator: Zobel, W.
Partner: UNT Libraries Government Documents Department

A THEOREM AND ITS APPLICATION TO FINITE TAMPERS

Description: A theorem is derived which is useful in the analysis of neutron problems in which all neutrons have the same velocity. It is applied to determine extrapolated end-points, the asymptotic amplitude from a point source, and the neutron density at the surface of a medium. Formulas for the effect of finite tampers are derived by its aid, and their accuracy is discussed.
Date: August 15, 1946
Creator: Feynman, R.P.
Partner: UNT Libraries Government Documents Department

Terminal Report on the Mighty Mouse Highflux Research Reactor Project

Description: The research and development program pertinent to the conceptual design and ultimate construction at ANL of an advanced research reactor with a peak thermal flux of 5 x 10/sup 15/ n/cm/sup 2//sec is documented. The basic reactor complex, the problems involved, the various approaches pursued, the present status and estimated cost of the project, along with recommendations for future research and development essential to the successful culmination of the project are described. The reactor is moderated with D,Oand has a core life of 120 hours at 250 Mw, (W.D.M.)
Date: September 1, 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Dickson, R. F.; Heineman, J. B.; Kelber, C. N. et al.
Partner: UNT Libraries Government Documents Department