63 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Liquid Flow"  
Results: 1 - 24 next
open access

Expansion program 190 Building studies results

Description: It is the objective of this study to investigate preliminary expansion program requirements for process water, as supplied by 190 Building equipment; from the point of view of practical pumping, flywheel and pump suction head requirements. These requirements are to be determined at this time in such a form and accuracy as to be useful in refined estimating for budget study purposes. In order to obtain the objectives of this study at this time it has been decided to consider five different condi… more
Date: November 25, 1959
Creator: Quackenbush, C. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculation of K reactor flow decay transient

Description: The process water pumping system for the K-reactors consists of six parallel sets of two series-connected pumps. A BPA outage could sever the power to all pumps. It is of major concern to known how the reactor flow decays with time following the power severance. The following analysis gives the general solution of this problem without recourse to the assumptions which have been used heretofore. The solution of the decay problem was programmed on the IBM 709. The program will give the flow trans… more
Date: September 17, 1959
Creator: Massena, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of an Eddy-Current Brake for a Sodium-Cooled Nuclear Power Reactor

Description: Two eddy-current electromagnets to act as brskes were designed and installed in the sodium-cooled nuclear pcwer reactor SRE to throttle sodium flow throughout the reactor after shutdown in order to maintain a constant reactor temperature gradient. One brake was used on the primary piping system, the other on the secondary system. It was determined that the eddy-current brake should cause a dragging pressure of 0.3 psi at a flow rate of 12 gal/min. The flux density necessary to produce this pres… more
Date: July 10, 1958
Creator: Baker, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PULSE COLUMN DESIGN

Description: A stagewise approach was used in a theoretical analysis of pulse columns. In the analysis the column was arbitrarily divided into discrete stages comprising that part of the column between two adjacent perforated plates. The operation of the pulse column was described mathematically using material balance equations, and a design method was derived which used two stage lines and two operating lines, one set for the pulse generator upstroke and one set for the downstroke. Assuming equilibrium con… more
Date: November 1, 1958
Creator: Burkhart, L.E. & Fahien, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FEASIBILITY OF PARTIAL CHEMICAL CONTROL FOR THE SM-2. SM-2 (FORMERLY APPR- 1B) DESIGN PROGRAM, TASK 12-CHEMICAL CONTROL

Description: Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance. Based on a review of existing information, boric acid was chosen as the reference soluble poison. It was shown that 60% of the burnable B/sup 10/ in the fuel element matrix could be replaced by soluble B/sup 10/ in the coolant without impairing plant stability during load transients. The feasibility of improving power distribution an… more
Date: May 15, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HYDROCLONE PERFORMANCE IN THE SOLVENT RECOVERY SYSTEM OF THE THOREX PLANT

Description: Tests on 1-gpm and 0.5-gpm hydroclones showed them to be unnecessary. Solvent-aqueous phase separation, although effective when optimized, was infrequently required. The 1-gpm hydroclone produced better water separation than the 0.5-gpm hydroclone for similar control parameters. Decontamination factors for widely varying flow conditions ranged from 1 to 3. Introduction of water into the hydroclone feed stream had no effect on decontamination or particle removal. (auth)
Date: March 31, 1958
Creator: Cerny, J. III
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamic Analysis of Natural Circulation Boiling Water Power Reactors

Description: Linear Feedback Control Theory is used to analyze the small-signal dynamic behavior of direct cycle, natural circulation boiling water reactor systems. Transfer functions for thermodynamic and hydraulic effects are derived in terms of reactor core and vessel dimensions. They are used to construct a theoretical system block diagram for the EBWR. (auth)
Date: March 1, 1958
Creator: Beckjord, E.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FLUIDIZATION CHARACTERISTICS OF PARTICULATE FILTER MEDIA

Description: Predictions of water velocities at which fluidization and massive entrainment of filter media (sea sand, Ottawa sand, silica, and alumina) will occur in special filter beds are presented. Pressure gradients in the various fluidized beds and the maximum bed expansions expected are tabulated. (auth)
Date: June 12, 1958
Creator: Lee, W.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A MOLTEN SALT NATURAL CONVECTION REACTOR SYSTEM

Description: Fuel-salt volumes external to the core of a molten-salt reactor are calculated for a system in which the fuel salt circulates through the core and primary exchanger by free convection. In the calculation of these volumes, the exchanger heights above the core top range from 5 to 20 ft. Coolants considered for the primary exchanger are a second molten salt and helium. External fuel holdup is found to be the same with either coolant. Two sets of terminal temperatures are selected for the helium. T… more
Date: February 1, 1958
Creator: Romie, F.E. & Kinyon, B.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Density Monitor for Purex HA Column

Description: A densimeter system is described which was developed for use on HA column. Reproducibility of instrument readings is plus or minus 2 1/2% of recorder span for pulser frequencies of 44 to 104 cycles per minute. The effects of column pulsations and column static pressure at the feed point are small. Simulated column feed point static pressure of 10 psig caused improved precision due to added damping of float oscillations. (auth)
Date: July 16, 1958
Creator: Huck, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Let-Down System Design for Homogeneous Reactors

Description: A study was made to determine the feasibility of designing a gas let- down system for homogeneous reactors, in which the pressure is taken through a fairly long tube rather than across a throttling valve. A schematic design of such a system is shown for the HRT in which the letdown stream passes through parallel tubes. Control is effected by the cutting in or out of tubes as is needed. Calculations indicate such a design is feasible. It is recommended that experimental work be done before the a… more
Date: November 1, 1955
Creator: Aven, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Model Study of the Pressure Drop Relationships in a Typical Fuel Rod Assembly

Description: A study was made of hydraulic characteristics of Yankee-type fuel rod assemblies using experimental and analytical methods. Two scale model fuel assemblies utilizing both ferrule and strap type arrangements were constructed and tested at atmospheric pressure and room temperature. Analytical methods using semiempirical relationships are substantiated by experimental results for both the fuel assembly having strap-type spacers and the fuel assembly having cylindrical ferruletype spacers. The expe… more
Date: February 1, 1959
Creator: Berringer, R. T. & Bishop, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THOREX PILOT PLANT: CRITICALITY REVIEW OF THE THOREX PILOT PLANT USING THE INT-23 PROCESS

Description: The results of a criticality review of the ORNL Thorex pilot plant are presented for the condition where a low TBP (INT-23) flowsheet is used in recovering U/sup 233/ from irradiated thorium. Criticality control will be maintained by limiting the U/sup 233/ inventory in the solvent extraction system to less than 550g by means of streamvolume and U/sup 233/ material balances determined at 8 hr intervals. Equipment modification and improved operating procedures for safe plant operation are outlin… more
Date: July 1, 1958
Creator: McDuffee, W.T. & Yarbro, O.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Correlation of Cavitation Inception Data for a Centrifugal Pump Operating in Water and in Sodium Potassium Alloy (NaK)

Description: For the centrifugal pump under investigation, the static head at pump suction, in feet absolute, at cavitation inception was correlated for water and for 1500 F NaK on the basis of the differences of the vapor pressures of the two liquids. The difference between the vapor pressure of water and NaK, for the same conditions of pump speed and liquid flow, was added to the water-test cavitation inception value, and this estimate proved to be a good approximation to the experimental value found for … more
Date: December 11, 1958
Creator: Grindell, A. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EBR-I, MARK III-DESIGN REPORT

Description: Under severe operating conditions, the Experimental Breeder Reactor was observed to exhibit oscillatory power characteristics and periods of prompt positive reactivity. Investigations of these characteristics resulted in the meltdown of Core-II and the design of a more suitable Core-III, with rod bowing eliminated and greater coolant flow control. The design of the core. rods, assemblies. and matrices is presented, and its control and cooling systems are described. (D.E B.)
Date: March 1, 1958
Creator: Rice, R.E.; Curran, R.N.; McGinnis, F.D.; Nevick, M. & Thalgett, F.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen