33 Matching Results

Search Results

Results: 1 - 24 next
open access

THE FERRITE BIASING SYSTEM FOR THE RADIO FREQUENCY CAVITIES OF THE PRINCETON-PENNSYLVANIA 3 Bev PROTON SYNCHROTRON

Description: A description is given of the ferrite biasing system for the four tuned radio frequency cavities of the synchrotron. Each ferrite loaded double cavity has a single turn bias winding which is driven to a peak current of 13,500 amperes by a push-pull transformer arrangement. There is automatic tap changing of the transformer to accommodate the variable impedance load (for power considerations). The programming and frequency response of the system have to be such that each cavity can operate as th… more
Date: August 29, 1962
Creator: Rees, G.H.
Partner: UNT Libraries Government Documents Department
open access

The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

Description: A detailed 4urvey of the radiation from the N.S. Savannah shield was made. The study was accomplished with the reactor at its full power of 69 Mw during a cruise of 2821 miles. The results of the detailed shield survey show that the design dose rate of 0.5 rem/yr for passenger spaces is not exceeded in any region to which passengers have access. ln the area restricted to crew access the design dose rate of 5.0 rem/yr is nowhere exceeded except in a small region on D'' deck in a room to which en… more
Date: August 29, 1962
Creator: Blizard, E.P.; Blosser, T.V. & Freestone, R.M. Jr.
Partner: UNT Libraries Government Documents Department
open access

HEAD-END TREATMENT OF LOW LEVEL WASTES PRIOR TO FOAM SEPARATION

Description: Calcium-magnesium precipitation apparatus was used to reduce the concentrations of these elements in ORNL tap water, used as a substitute for waste water of low level of radioactivity, prior to strontium removal by foam separation. With and without alkali and flocculator chambers and with a stirred sludge of ratio height to diameter equal to 1/1 to ~4/1, use of 5 x 10/sup -3/ M each of NaOH and Na/sub 2/CO/sub 3/ and 2 ppm Fe/sup 3+/ reduced the dissolved Ca + Mg concentrations to 1 to 2 ppm as… more
Date: May 29, 1962
Creator: Schonfeld, E. & Davis, W. Jr.
Partner: UNT Libraries Government Documents Department
open access

Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments

Description: Techniques for conditioning of Ta filaments for improved bonding and emission with a Ta metal powder-Ta/sub 2/O/sub 5/ mixture are described. A porous Ta metal layer is deposited which restricts sample to the filament. Metal- oxide ion emission is enhanced with additional Ta/sub 2/O/sub 5/ to the porous layer. Reduction of fractionation through action of liquid Ta/sub 2/O/sub 5/ is discussed in particular for Sr+ emission. Use of conditioned filaments for rapid U concentration analysis with a s… more
Date: June 29, 1962
Creator: Goris, P.
Partner: UNT Libraries Government Documents Department
open access

High-Temperature Reactions of Type 304 Stainless Steel in Low Concentrations of Carbon Dioxide and Carbon Monoxide

Description: Compatibility studies of type 304 stainless steel in helium containing low concentrations of CO and CO/sub 2/ were conducted. The oxidation rates were insensitive to impurity concentrations between 0.0006--0.3 vol% in the temperature range 400--1000 deg C when P/sub co2/P/sub co/ was less than 0.66. Ratios above this value resulted initially in a slow oxidation rate, but was followed by an accelerated attack. The incubation period for the break-away varied with the P/sub co2//P/sub co/ ratio an… more
Date: August 29, 1962
Creator: Inouye, H.
Partner: UNT Libraries Government Documents Department
open access

Pathfinder Atomic Power Plant. Thermal and Hydraulic Design of the Pathfinder Boiling Water Integral Nuclear Superheating Reactor

Description: A thermal and hydraulic design investigation of the Pathfinder Reactor, including analytical and experimental determinations, as well as a complete set of performance calculations, was carried out. A detailed analysis of the reactor energy balance was conducted. Results of the analyses indicated that the reactor will perform within the limits of the material design criteria and operational requirements. Fuel element temperatures are not excessive under the worst combination of circumstances. Th… more
Date: August 29, 1962
Partner: UNT Libraries Government Documents Department
open access

HEXAFLUORIDES OF MOLYBDENUM, TUNGSTEN AND URANIUM. II. REACTIONS WITH LIQUID AND GASEOUS DINITROGEN TETROXIDE

Description: Molybdenum and tungsten hexafluorides form the solids nitrosylium pentafluoroxymolybdate(VI) and -tungstate(VI), respectively. Uranium hexafluoride gives nitrosylium hexafluorouranate(V) STANOUF/sub 6/!, the same salt that it forms with nitric oxide. (auth)
Date: January 29, 1962
Creator: Geichman, J. R.; Smith, E. A.; Swaney, L. R. & Ogle, P. R.
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Technology Quarterly Progress Report, January-March 1962

Description: The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissol… more
Date: June 29, 1962
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
open access

Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962

Description: The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, wh… more
Date: June 29, 1962
Partner: UNT Libraries Government Documents Department
open access

Data Analysis Techniques for Gamma-Ray Scintillation Spectrometry

Description: A series of computer programs are described which Were successfully applied to the reduction of pulse-height data using digital computers. Calculations carried out by these programs include: determination of pulse height vs energy response of an NaI detector; calculation of coincidence sum spectra; and the analysis of complex pulse-height spectra to obtain energies and relative intensities of individual gamma rays or relative abundances from a mixture of radionuclides. Measurement problems and … more
Date: May 29, 1962
Creator: Heath, R. L.
Partner: UNT Libraries Government Documents Department
open access

Characteristics of splines for fine distribution control

Description: The introduction of poison splines as operating aid at the Hanford reactors has resulted in an impressive production increase. This increase is mainly due to the effect on startup control and to better equilibrium flux shaping. In providing sufficient reactivity effect for startup control, however, present splines sometimes increase rather than decrease flattening and distribution control problems when utilized during equilibrium operation. In additional being of constant poison strength along … more
Date: January 29, 1962
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
open access

Physics aspects of operation in event of a large reactivity loss

Description: The following information was prepared to assist the physicist who encounters a large reactivity lass as in a water soaked lattice or a more permanent loss as in the case of balls remaining in the pile after a ball drop. The discussion is based on experience gained during F Reactor`s severe water leak of July 27, 1961.
Date: January 29, 1962
Creator: Heiple, R. B.
Partner: UNT Libraries Government Documents Department
open access

Proposal for charging the eighth fuel rupture experiment, GEH 10-57

Description: The objective of this test is to prove a new method of intentional rupturing of fuel elements under conditions of high specific powers and central core temperatures. The fuel will be the inner component of an NPR fuel element assembly. Permission to change one tubular fuel element (GEH-10-57) into the GEH-P7 loop is requested. A hydraulic cylinder will be attached to the fuel basket assembly. The hydraulic cylinder will be used to move a cutter along the outer surface of the fuel element. The c… more
Date: January 29, 1962
Creator: Kaulitz, D. C. & Call, R. L.
Partner: UNT Libraries Government Documents Department
open access

Instrumentation studies, Status report

Description: Two computer codes (1- and 6-node models) were used in the calculations. For the 1-node model, standard reactor kinetics,heat transfer, and instrument delay equations were programmed for analog and digital computers; effects of full-pile reactivity insertions were calculated. The 6-node model contains the time-dependent diffusion equations and heat transfer and instrument delay equations; it was programmed for the analog computer only, and was used to calculate effects of local reactivity inser… more
Date: March 29, 1962
Creator: Stiede, W. L. & Monnie, D. I.
Partner: UNT Libraries Government Documents Department
open access

KER-4 operating report: Test K-4-13, PT IP-477-A

Description: The purpose of Test K-4-13 detailed in this report was to evaluate the behavior of N Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor during Phase I) equilibrium operation. Specific objectives of Test K-4-13 were: Measurement of fuel distortion and swelling; Evaluation of irradiation damage to the jacket uranium bond and to the uranium core; and Evaluation of the performance of the fuel element support system.
Date: October 29, 1962
Creator: Davis, J. P.
Partner: UNT Libraries Government Documents Department
open access

Production test IP-541-A reactor effluent studies

Description: The objective of this test is to determine the concentrations of radioisotopes in the effluent from a Zircaloy tube and an aluminum tube when both are charged with Zircaloy clad fuel elements and cooled with deionized water. Deionized water is currently being used as the coolant for a Zircaloy and an aluminum tube at KE Reactor. To date the fuel for these tubes has been aluminum clad. Progress is being made in assessing the relative importance of fuel element film and tube film on the radioisot… more
Date: October 29, 1962
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
open access

Assembly and performance of fuel elements for H-Reactor E-N demonstration load. Final report

Description: Preparation of enriched fuel elements and target (N) elements for a full H-Reactor E-N demonstration loading was authorized in April, 1960. The objective of this loading was to demonstrate the feasibility of operating a Hanford reactor economically as a plutonium-tritium producer to increase over-all conversion ratio and diversify product output. Irradiation of the E-N load began in May, 1961 and was completed in January, 1962.
Date: May 29, 1962
Creator: Blanton, W. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
open access

A Comparison of the Nuclear Defense Capabilities on Nuclear and Coal-Fired Power Plants. Fuel Cost Study Various Reactors at 100 and 300 Mwe

Description: Appendices C and D may further be identified as SL1925 and CF-61-12- 20(Rev.), respectively. A comparative report is presented in which the economics and feasibility of plant protection from nuclear attack by plant hardening, remote siting, and utilization of optional fueling concepts for the coal-fired plant are evaluated. (J.R.D.)
Date: May 29, 1962
Creator: Gift, E. H.
Partner: UNT Libraries Government Documents Department
open access

MOUND LABORATORY PROGRESS REPORT FOR JUNE 1962

Description: Research and development progress is reported on plastics, analytical methods, radioelements, isotope separation and purification, reactor fuels and materials developmert, Ranger x-ray sensor program, and SNAP a. (M.C.G.)
Date: June 29, 1962
Creator: Grove, G.R.; Jones, L.V. & Eichelberger, J.F.
Partner: UNT Libraries Government Documents Department
open access

Heating in the shield

Description: No Description Available.
Date: March 29, 1962
Creator: Clement, J.D.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen