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Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2

Description: The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification… more
Date: July 21, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

De-entrainment on vertical elements in air droplet cross flow. [PWR]

Description: De-entrainment phenomena on vertical elements in air-water droplet cross flow are generated using a horizontal array of water spray nozzles and a draft-induced wind tunnel. These conditions are used to obtain experimental values of the de-entrainment efficiency of isolated elements (25.4-, 63.5-, and 101.6-mm-diam cylinders and a 76.2-mm-square tube), and of an array of 101.6-mm-diam cylinders. A flow model is developed that extrapolates the de-entrainment efficiency of isolated elements throug… more
Date: January 1, 1980
Creator: Dallman, J.C. & Kirchner, W.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1, 1979-February 29, 1980

Description: Information is presented concerning bundle geometry with wrapped and bare rods; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.
Date: January 1, 1980
Creator: Todreas, N.E.; Golay, M.W. & Wolf, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Waste Treatment and Disposal Progress Report for June and July 1961

Description: 7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scaven… more
Date: October 24, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

REACTOR MAIN COOLANT LOOP

Description: A parametric study was made for the POPR with temperature gradients of 610 to 670 deg F and 6l0 to 684.5 deg F at organic flow rates of 17.8 x l0/sup 6/ and l4.4 x l0/sup 6/ lbs/hr, respectively; and steam turbine conditions at the throttle of 600 and 650 deg F at 800 to l200 psig. The study was made to obtain the most economical layout of the main heat transfer loop system. (B.O.G.)
Date: August 1, 1961
Creator: Terpe, G.R. & Katz, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column

Description: Over-all mass transfer coefficients were determined independently of the interfacial area by considering the operation of the pulse column to be a stage- wise process. The calculated coefficients describe only the operation of the pulse column for the free rise of organic droplets through a stage, since in the downstroke the aqueous phase passes through the organic phase in the form of rivulets preferentially wetting the plates. The driving force for transfer was based on the aqueous phase conc… more
Date: November 1, 1960
Creator: Konopik, A. E. & Burkhart, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Measurement and analysis of flow wall shear stress in an interior subchannel of triangular array rods. [LMFBR]

Description: A simulated model of triangular array rods with pitch to diameter ratio of 1.10 (as a test section) and air as the fluid flow was used to study the LMFBR hydraulic parameters. The wall shear stress distribution around the rod periphery, friction factors, static pressure distributions and turbulence intensity corresponding to various Reynolds numbers ranging from 4140 to 36170 in the central subchannel were measured. Various approaches for measurement of wall shear stress were compared. The meas… more
Date: August 1, 1977
Creator: Fakori-Monazah, M.R. & Todreas, N.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A study of steady-state steam-water counterflow in porous media

Description: Vapor-liquid counterflow in porous media arises in processes such as heat pipes, oil recovery and geothermal systems. Previous studies analysed these phenomena in separate contexts. This paper presents a unified description from which previous models result as limiting cases. The analysis includes capillarity, heat conduction, and Kelvin effects. The importance of each term to various processes is examined. Significantly, it is found that the critical heat flux is not constant but increases wit… more
Date: February 1, 1990
Creator: Satik, C.; Parlar, M. & Yortsos, Y.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SNAP Programs: Task 6--Fuel Technology Development Program. Quarterly Progress Report No. 7, April 1 Through June 30, 1961

Description: Progress made in the development of isotope power sources for thermoelectric and thermionic conversion to electrical energy is reported. The Heavy Elements Processing Facility for processing americium and fabricating americium capsules for irradiation was opened and hot operation was begun. Modifications to the americium purification system were completed and checkout operations were begun. Process specifications were established for dissolution of the irradiated capsules and the major equipmen… more
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

GCFR core thermal-hydralic design

Description: The approach for developing the thermal-hydraulic core assembly designs for the gas-cooled fast reactor (GCFR) is reviewed, and key considerations for improving the core performance at all power and flow conditions are discussed. It is shown how the thermal-hydraulic core assembly designs evolve from evaluations of plant size, material limitations, safety criteria, and structural performance considerations.
Date: May 1, 1980
Creator: Schleuter, G.; Baxi, C.B. & Bennett, F.O.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Flashing inception in flowing liquids

Description: The inception of net vaporization in flashing flows is examined. It is suggested that the flashing inception can be expressed as two additive effects. One is due to the static decompression which is a function of the initial temperature and also of the expansion rate. The other effect which is a function of Reynolds number and flashing index, is due to the turbulent fluctuations of the flowing liquid. It is shown that by taking a three standard deviation band on the turbulent velocity fluctuati… more
Date: April 1, 1980
Creator: Jones, O. C., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962

Description: During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of mol… more
Date: June 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Results and predictions of scaled, nuclear large break loss-of-coolant experiments. [PWR]

Description: Two 200% cold leg break loss-of-coolant experiments performed in the LOFT facility have exhibited early core-wide quenches which were not predicted by the RELAP4/MOD6 code. Posttest studies have shown that while the critical flow model used significantly affects the hydraulic calculation, the principal reason for not predicting the quench behavior lies in the area of post-CHF heat transfer. The ability of the code to calculate quenches using a modified heat transfer surface is demonstrated, the… more
Date: January 1, 1980
Creator: Grush, W. H.; Lin, J. C.; Linebarger, J. H. & Nelson, R. A. Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR]

Description: The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the… more
Date: March 21, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TECHNICAL DESCRIPTION OF A SODIUM-COMPONENT TEST INSTALLATION

Description: The instellation is designed primarily for operational testing of Na- heated steam generators and intermediate heat exchangers suitable as prototype components for large, Na-cooled power plants. Other types of Na components can also be tested in the facility. The instellation consists of a 35-Mwt gas-fired Na heat source, a main primary-Na system, a main secondary-Na system, a water- steam system, and a set-up for heat rejection to air. (J.R.D.)
Date: January 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HRT-CHEMICAL PLANT RUN 21 SUMMARY

Description: The multiple hydroclone system removed l83 grams of corrosion product solids in l814 hours of operation during reactor run 2l. The low removal rate was attributed to plugging of multiclone feed ports that presumably occurred during the latter part of run 20. After modifications to the reactor core and removal of the multiclone unit at the end of run 21, the reactor core was backflushed with the flow direction in the core loop reversed. During this period, the single hydroclone removed 205 grams… more
Date: February 12, 1962
Creator: Yarbro, O.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Computational and experimental methods for enclosed natural convection

Description: Two computational procedures and one optical experimental procedure for studying enclosed natural convection are described. The finite-difference and finite-element numerical methods are developed and several sample problems are solved. Results obtained from the two computational approaches are compared. A temperature-visualization scheme using laser holographic interferometry is described, and results from this experimental procedure are compared with results from both numerical methods.
Date: October 1, 1977
Creator: Larson, D.W.; Gartling, D.K. & Schimmel, W.P. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamic Simulation of Multi-Pass Pressurized Water Nuclear Power Plants by Analog Computer Techniques

Description: A kinetic model of the primary loop of a multi-pass pressurized water reactor power plant is developed to evaluate, by analog computer techniques, the transient response characteristics under conditions of steam generator load and reactor control rod perturbations. Using the 2-pass 28 Mw(t) SM-2 reactor as a typical plant, transient behavior patterns are illustrated and examined for a variety of load inputs, variations in plant constants, and analog model simplifications. (auth)
Date: June 1, 1961
Creator: Brondel, J. O.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
open access

Spert I Destructive Test Program Safety Analysis Report

Description: The water-moderated core used for destructive experiments is mounted in the Spent I open-type reactor vessel, which has no provision for pressurization or forced coolant flow. The core is an array of highly enriched aluminum clad, plate-type fuel assemblies, using four bladetype, gang-operated control rods. Reactor transients are initiated at ambient temperature by step-insentions of reactivity, using a control rod which can be quickly ejected from the core. Following an initial series of stati… more
Date: June 15, 1962
Creator: Spano, A. H. & Miller, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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