UNT Libraries Government Documents Department - 23 Matching Results

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An Analysis of the Inherent Stability of the EOCR

Description: The inherent stability of the EOCR at full power, exclusive of the heat exchanger, is investigated. Space and time dependent differential equations and transfer functions for the nuclear and thermal processes occurring in the reactor core and vessel are derived. Reactor stability is analyzed by application of the Nyquist stability criterion. The results show that the EOCR has an extremely large margin of inherent stability. (auth)
Date: August 24, 1962
Creator: Gossmann, S.R.
Item Type: Refine your search to only Report
open access

Boron Carbide-Graphite Nuclear Control-Rod Material: Preparation, Thermal Stability, and Irradiation Evaluation

Description: Boron carbide-graphite nuclear control-rod materials containing up to 45 wt% B were prepared by hot-pressing techniques. The densities of these compacts decreased with increasing B content. Compact strengths, however, were noticeably increased with B content of 20 wt%, suggesting that the B acts as a sintering aid. Thermal stability was evaluated by annealing compacts under a variety of temperature and atmospheric conditions. The upper limit of the ioss of 13 was 5% to 10%~ in 200 hr at 2000 de… more
Date: April 24, 1962
Creator: Goeddel, W. V.; Lonsdale, H. K. & Meyer, R. A.
Item Type: Refine your search to only Report
open access

Chemical Processing Technology Quarterly Progress Report, April-June 1962

Description: Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in determination of dissolution rates over a wide range of conditions. The addition of oxidants to 4.8M hydrofluoric acid used for the continuous dissolution of 3% uranium-Zircaloy- 2 fuel decreased the amount of uranium-containing residue in the dissolver at the expense of a decreased dissolution rate.… more
Date: September 24, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
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Corrosion of Steel Pilings in Soils

Description: From Introduction: "In this paper are presented the results obtained to date from the inspections of steel pilings. The investigation will be continued by additional inspections of pilings in other parts if the country in order to cover a wider range of soil environments."
Date: October 24, 1962
Creator: Romanoff, Melvin
Item Type: Refine your search to only Report
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Dissociation and Ionization of H$Sub 2$$Sup +$ by Electrons and Protons

Description: <><DSN>16:009503<ABS>Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuum arcs; ion production, acceleration, and injection; plasma theory and computations; magnetics; and vacuum system techniques. Separate abstracts were prepared for the eight sections. (B.O.G.) 9504(Faye unscannable abstract)
Date: January 24, 1962
Creator: Alsmiller, R. G., Jr.
Item Type: Refine your search to only Report
open access

Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961

Description: The design status of the Experimental Fast Ceramic Reactor (EFCR) is described for the period up to October 31, 1961. The primary purpose of the facility is to study the dynamic behavior of a fast ceramic reactor, including the experimental demonstration of the effectiveness of the Doppler coefficient in limiting the power excursion following a rapid insertion of reactivity.
Date: April 24, 1962
Creator: Horst, K. M.
Item Type: Refine your search to only Report
open access

A feasibility study: The application of cooling towers for reduction of Hanford Plant heat load to the Columbia River

Description: Hanford production reactor operation requires the rejection of very large heat loads. At the present time the heat load is rejected to the Columbia River by the reactor effluent. At low river flows the hot effluent can have appreciable effects on river temperatures. The purpose of this study is to evaluate the feasibility and costs of Cooling Towers as a means of reducing the heat load rejected to the Columbia River. After evaluation of published information, available data, and Hanford plant c… more
Date: August 24, 1962
Creator: Peck, G. E.
Item Type: Refine your search to only Report
open access

General parameter study of a bare, cylindrical reactor having the same materials as Tory II-C

Description: This memorandum describes studies undertaken to investigate the properties of Tory II-C with the aims of reducing weight and size and in increasing performance. Space and weight limitations aboard existing sea-going launch vehicles required this general parameter study which utilizes a bare, cylindrical reactor having the same materials as Tory II-C.
Date: August 24, 1962
Creator: Stubbs, T.
Item Type: Refine your search to only Report
open access

Hallam Nuclear Power Facility Preoperational Test Completion Report Dry Criticality

Description: A dry criticality test was carried out to determine the minimum critical mass of the HNPF Core without sodium. A subcritical calibration of the central control rod was performed and the relative reactivity worths of the inner ring of six control rods were determined. The extrapolated critical loading for the various plots after each incremental fuel loading with all rods out is shown. A tabulation is presented of multiplication data taken throughout the dry critical test. In order to find the r… more
Date: February 24, 1962
Creator: Kempt, H. C. & Corcoran, W. P.
Item Type: Refine your search to only Report
open access

Nuclear Safety Program Semiannual Progress Report for Period Ending June 30, 1962

Description: Progress in nuclear safety research and development is reported. Topics covered include: reactivity effects of fuel displacements in a pool-type reactor, release of fission products on out-of-pile melting of reactor fuels, release of fission products on in-pile melting of reactor fuels, fission product transport evaluations, characterization and control of accident-released fission products, nuclear safety pilot plant, preparation of reactor containment hardbook, and radiochemical plant safety … more
Date: August 24, 1962
Item Type: Refine your search to only Report
open access

PT IP-416 measurement of the horizontal rod strength at H Reactor. Final report

Description: The object of this test was to obtain data concerning the reactivity of the horizontal rods in the E-N fuel loading at H Reactor. An accurate calibration of the control rods could then be used to provide a more accurate measurement of the other reactivity variables associated with the E-N loading. A comprehensive rod calibration test was performed at H Pile in 1957. Results of the present test, needed because of the ``blacker`` E-N fuel in the pile, have been normalized to the 1957 test results… more
Date: January 24, 1962
Creator: Vaughn, A. D.
Item Type: Refine your search to only Report
open access

REACTIONS OF SOLVATED IONS. Final Report

Description: >Brief summaries are presented on isotopic dilution studies on salts dissolved in JCH/sub 3/OH, studies on metal and metal salts in solvents of the amine type, and studies on phosphato complexes of the pentammine Co(III) series. A list of papers published on reactions of solvated ions is included. (N.W.R.)
Date: September 24, 1962
Creator: Taube, H.
Item Type: Refine your search to only Report
open access

Recrystallization of Beta-Heat-Treated Dingot-Uranium Cores. Topical Report

Description: Annealing beta-heat-treated production-size dingoturanium core blanks in the high alpha range (1150 to 1200 deg F) produced a fine, equiaxed grain size by a recrystallization process. The extent of recrystallization is dependent upon the rate of cooling through the beta-to-alpha transformation, the time and temperature of annealing, and whether or not impurities that retard grain growth are present. The cooling rate through the beta-to-alpha transformation was varied by using a range of beta te… more
Date: August 24, 1962
Creator: Guyer, R. R. & Neumann, N .F.
Item Type: Refine your search to only Report
open access

Results of production test IP-528-I, F Reactor high tank drawdown test

Description: A continued decrease in flow measured during the periodic high velocity flushes indicated that corrosion buildup in the high tank discharge lines was deceasing backup flow to the reactor. An accurate determination of the high tank flow rate to the reactor was needed to evaluate present back-up adequacy. Riser pressure and flow rate were also measured with throttled high tank discharge lines to establish the low flow and critical portion of the reactor hydraulic characteristic curve. This report… more
Date: October 24, 1962
Creator: Lessor, L. C.
Item Type: Refine your search to only Report
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