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Fission and Corrosion Product Activities in Main Coolant and Atmosphere of the Vapor Container

Description: Fission products, which may leak from the fuel and activated corrosion products from stainless steel surfaces, influence the design of several systems which support the main coolant system. Since the radioactivity in the main coolant resulting from these impurities must be limited to reasonable levels during operation, a purification system becomes important. Air conditioning of the vapor container as a result of possible main coolant leakage may be necessary during and after operation to remov… more
Date: May 15, 1958
Creator: Kresny, H. S. & Haga, P. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of S and P 1963, the Pebble Bed Reactor

Description: Sanderson and Perter, under contract to the AEC, prepared a design feasibility study for a pebble-bed reactor steam power plant of 125-Mw(e) capacity. The design problems, economic considerations, and required research and development programs were reviewed by ORNL. It is concluded that the design shows promise of being economically competitive if the following conditions are met: (1) U/sup 233/ could be made available for use as a burner rather than as a breeder; (2) the contamination problems… more
Date: July 17, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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STUDIES OF UPPER-PLENUM COOLANT CIRCULATION IN A QUARTER-SCALE AIR-FLOW MODEL OF THE PWR

Description: Air-flow studies were run in a quarter-scale flow model of the PWR to determine distribution of flow throughout the upper-plenum region with two different hold-down-barrel designs. With each hold-down barrel, flow paths were determined for operation with four loops, three loops, two opposed loops, and two adjacent loops. Exploration of flow patterns and velocities throughout the upper plenum showed that circulation of coolant throughout the upper plenum was satisfactory with either of the hold-… more
Date: March 18, 1958
Creator: Orban, A.R. & Hazard, H.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A STUDY OF HEAVY WATER CENTRAL STATION BOILING REACTORS (CSBR)

Description: Reactors designed for economic operation in stationary central power plants were studied. Certain objectives presented themselves as being of particular importance if an attractive economy were to be obtained. These objectives arei use of ceramiic (UO/sub 2/) rather than inetallic fueI; use of natural uranium; high conversion ratio; long fuel life; natural convection for heat transfer; production of superheated steam; a high power output; a limited size of pressure tank; fueI handling without u… more
Date: September 1, 1958
Creator: Treshow, M.; Shaftman, D.; Templin, L.; Petrick, M.; Hoglund, B. & Link, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SELECTED VALUES OF THE PHYSICAL PROPERTIES OF VARIOUS MATERIALS

Description: Selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis are presented. In most cases. values for thermal conductivity specific heat, demasity, viscosity, and Prandti numbers are given as functions of temperature. A table of room temperatures values of some properties was compiled on materials for which data as a function of temperature were not found. A short list of references to additional physical property data o… more
Date: September 1, 1958
Creator: Tebo, F.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analog Computer Study of the Operation of the Gas-Cooled Loop on the Oak Ridge Research Reactor

Description: An annlog computer study of the ORR gas-cooled loop was made. The effects on fuel and gas temperatures of changing gas (nitrogen) flow rates, turning the heater on and off, and inserting or removing the fuel were determined. It was found that the temperature of the sample, if fuel, could be raised more rapidly than it could be reduced, and that the temperature could be reduced faster with high rates of flow. All of the equations used in building up the computer are given, and some of them are d… more
Date: July 1, 1958
Creator: Green, F. P.; Neill, F. H.; Short, B. E. & Winton, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE SODIUM-COOLED, D$sub 2$O-MODERATED REACTOR (SDR). Status Report

Description: For presentation at the 1958 Nuclear Congress, Nuclear Science and Engineering Conference, March 17The experimental program was focused on the problems of containing the Na, of providing a barrier material with low neutron absorption cross section and an ability to withstand the action of hot Na, of developing an arrangement of this material which is mechanically adequate, and of demonstrating that an integrated barrier system can be safety operated under reactor tempernture and pressure condit… more
Date: January 1, 1958
Creator: Goldmann, K. & Leeper, C.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analyses of Experimental Power-Reactivity Feedback Transfer Functions for a Natural Circulation Boiling Water Reactor

Description: ABS>Experimental power-reactivity feedback transfer functions were calculated from the EBWR power transfer function measurements. A simplified model of the EBWR kinetics was developed, using an analog computer, and an analytic expression was obtained for the feedback function. The analytic solution was fitted to the experimental functions to obtain power coefficients and time constants for various modes of operation. These data were extrapolated, and a power transfer function was predicted for … more
Date: July 1, 1958
Creator: DeShong, J.A. Jr. & Lipinski, W.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HRE-3 PRESSURIZER DESIGN

Description: A conceptual design is presented for the HRE-3 core and blanket pressurization systems. In general, the systems are similar to the preliminary designs previously described. Flowsheets, conceptual sketches, and specification = for the major components are included. Estimation oi the D/sub 2/ concentration in the blanket is treated in detail. The design appears to be safe with regards to the d/sub 2/ explosion hazard. (auth)
Date: February 1, 1958
Creator: Bolger, J.C. & Maak, R.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Sodium Graphite Reactor Power Plant for CPPD

Description: The plant arrangement, component design, and the functions of various systems are described and illustrated. Relative estimated costs of the systems and major components are indicated. The reactor core is designed around requiremouts for 254 thermal megawatts, 950 deg F maximum sodium temperature, stainless steel clad graphite moderator blocks, and low enrichment (0.015 to 0.04 U/sup 235/) uranium fuel elements. The fuel cycle is described for the possible fuel elements. The fuel cost factors a… more
Date: October 31, 1958
Creator: Olson, R. L.; Gerber, R. C.; Gordon, R. B.; Ross-Clunis, H. A. & Stolz, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CHEMICAL INDICATIONS OF HRT MISBEHAVIOR IN RUN 17-A

Description: The cause and significance of the changes in chemical composition of the HRT fuel and changes in reactivity during operation, particularly in run 17A, were investigated. It was concluded that a rise in reactor power level causes deposition of U, Cu, and Ni in some hydrolytic process within the core circulation system in a region which is at a position between zero and average nuclear importance. The deposition requires several minutes to several hours and is relatively easily reversiable when t… more
Date: September 18, 1958
Creator: McDuffie, H.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Equations for Analog Computer Studies to Size the Reactor Plant Pressurizer

Description: The assumptions and equations used to conduct reactor plant load trnnsient studies on the analog computer are presented. The study was performed to determine the magnitude of reactor cooling water temperature and volume variations caused by secondary plant load transients, and to establish the size of the pressurizer which would be capable of limiting the cooling water pressure variations caused by the volume surges. (auth)
Date: October 15, 1958
Creator: Lyman, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and Analysis of a Mechanical Transition Joint Between Dissimilar Materials--Application to HRT

Description: The desigm and analysis of a mechanical transition joint between materials having different thermal coefficients of expansion are discussed. The analytical treatment is based primarily on the analysis of short cylinders. The specific desigm for the Zircaloy-2stainless steel core vessel joint in the HRT is discussed in detail. Brief summaries of preliminary designs and test results are included along with results obtained from the tests performed on the final design for the HRT. (auth)
Date: September 15, 1958
Creator: Cheverton, R.D. & Mauney, T.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DYE RETENTION TIME STUDIES IN MODELS OF POSSIBLE HRE-3 CONFIGURATIONS

Description: Dye hold-up time studies were completed for three 1/16-scale lucite models of possible HRE-3 configurations. The models studied had a spherical (#MF- 2) and a cylindrical (#MF-1)(core with flat heads on the pressure vessels. Model MF-2 was also run with a ''dished'' head on the pressure vessel (#MF-2D). Results for these models indicate a change from laminar to turbulent flow when the equivalent Reynolds number was within a range of 900 to 1,500. Better mixing was found in model MF-1 than in MF… more
Date: June 1, 1958
Creator: Mixon, W.R. & Claiborne, H.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Study of Decontamination Agents for Use in the Yankee Reactor

Description: A study of chemical decontamination agents for possible use in the Yankee Reactor is presented. The necessity for chemical decontamination is discussed along with the properties sought in an ideal cleaning solution. A survey of available decontamination information is presented together with a description of the experimental test progam carried out at the Westinghouse Atomic Power Department in an effort to develop new and improved chemical methods for the removal of oxide scals and radioactive… more
Date: November 1, 1958
Creator: Watkins, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Effect of Local Boiling on Pressure Drop and Flow Distribution in the Yankee Reactor Core

Description: Where local boiling can occur in a semi-open heterogeneous reactor core consisting of parallel flow channels, differences in the terms comprising the total pressure drop in the local boiling regions and in parallel adjacent regions canse flow redistribution in the reactor. This report covers the study of the effect of local boiling on the friction factor and momentum components of the total pressure drop. The local-boiling to single-phase friction factor ratio has a maximum value of 1.42 when a… more
Date: August 29, 1958
Creator: Bishop, A. A. & Berringer, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Flow Visualization Loop for Flow Pattern Studies in Reactor Models

Description: The installation of a milling yellow flow visualization loop has been completed. Milling yellow is an organic dye which when dissolved in water exhibits flow double refracting properties that permit visual observations of flow patterns. The equipment is to be used in qualitative studies of flow patterns in various models of reactor vessels and components. (auth)
Date: August 1, 1958
Creator: Mixon, W.R. & MacColl, H.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Description: Originally issued as S and P 1963A, Parts I and II. A design and feasibility study of a pebble bed reactorsteam power plant is presented, The reactor design which evolved from this study is a 125 Mwe heliumcooled two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam gene… more
Date: May 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CONSTRUCTION DESIGN OF EBR-II: AN INTEGRATED UNMODERATED NUCLEAR POWER PLANT

Description: The Argoune Experimentul Breeder Reactor-II is a completely integrated nuclear power plant which employs an unmoderated reactor as a heat source, and generates 20,000 kw of electricity. The integrated nuclear plant includes the fuel re-processing and fabrication cycle and thereby makes a signigicant contribution to power reactor techaology by operating on recycled fuel. The preliminary design of this plant was described at the First International Conference on the Peaceful Uses of Atomic Energy… more
Date: October 31, 1958
Creator: Koch, L. J.; Monson, H. O.; Simmons, W. R.; Levenson, M.; Verber, F.; Hutter, E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pressurized Water Reactor Program Technical Progress Report for the Period May 5, 1955 to June 16, 1955

Description: The current PWR plant and core parameters are listed. Resign requirements are briefly summarized for a radiation monitoring system, a fuel handling water system, a coolant purification system, an electrical power distribution system, and component shielding. Results of studies on thermal bowing and stressing of UO/sub 2/ are reported. A graph is presented of reactor power vs. reactor flow for various hot channel conditions. Development of U-- Mo and U-Nb alloys has been stopped because of the r… more
Date: October 31, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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