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Suggestion for High Pressure Letdown Device
A letdown valve design is described which reduces erosion of the sealing surfaces. It also provides for water flushing of the sealing surface before closing.
Date:
April 2, 1957
Creator:
Lyon, Richard Norton
Object Type:
Report
System:
The UNT Digital Library
Pressure Rise in HRT Shield Due to Reactor and Replacement heat Exchanger Rupture
.Recalculations were made of HRT cell pressures in the event of a simultaneous rupture of the reactor core vessel and the fuel and blanket heat exchangers. These calculations will be applicable after the replacement fuel heat exchanger is installed. The pressure rise in the cell is plotted as a function of time. A maximum cell pressure of 34 psig is achieved ~7 sec after rupture.
Date:
April 2, 1957
Creator:
Bolger, J. C.; Maak, R. O. & Gift, E. H.
Object Type:
Report
System:
The UNT Digital Library
A Preliminary Study of Molten Salt Power Reactors
A preliminary study of molten salt power reactors was made. The most promising fuel carrier salts were the fluorides and chlorides of the alkali metals, zirconium, and beryllium. The chlorides were found to have lower melting points but were less stable and more corrosive than the fluorides. A Li/sup 7/ F- - BeF/sub 2/ mixture with ThF/sub 4/ and UF/sub 4/appeared to perform best. Of the numerous alloys tested as container material, Inconel and a nickel-- molybdenum alloy INOR-8 appeared to be the most resistant to corrosion. To study the performance, safety, economics, and construction costs of a typical molten salt reactor, a reactor of specific type and size was chosen for study. The reference design reactor was a two-region homogeneous converter with a core salt of 70 mole% Li/sup 7/F and 30% BeF/sub 2. ThF/sub 4/ and enough VF/sub 4/ for criticality were added. Study indicated that a molten salt reactor would produce economical power, but the problem of developing a salt core and a container metal which would last for many years of operation needed further study. (M.C.G.)
Date:
April 29, 1957
Creator:
MacPherson, H. G.; Alexander, L. G.; Carrison, D. A.; Estabrook, J. Y.; Kinyon, B. W.; Mann, L. A. et al.
Object Type:
Report
System:
The UNT Digital Library
Second and Third Operating Test of HRT Core Vessel Transition Joint and Expansion Bellows Mockup
Second and third tests were conducted on an expansion bellows and Zircaloy-stainless steel transition joint assembly, duplicating that used in the core-pressure vessel assembly of the HRT. The assembly was exposed for 1140 hours in the second test and and 167 hours in the third to a solution containing 0.04m UO2SO4, 0.02m H2SO4, and 0.005m CuSO4 in a 100A dynamic corrosion loop under conditions simulating reactor startup, shutdown, and steady-state operation. Results indicated that the transition joint assembly as tested was mechanically sound and leak-tight. Pit-type corrosion continued on the expansion bellows where the upper retaining tangent contacts the bellows. Results are included of specimens exposed to the circulation solution during transition joint and bellows test.
Date:
April 30, 1957
Creator:
Greeley, R. S.; Ulrich, W. C.; Savage, H. C.; Griess, J. C. & Mauney, T. H.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report of the Solution Corrosion Group for the Period Ending April 30, 1957
A third test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel was completed. No additional mechanical deflections of the bellows were made, but 12 additional thermal cycles of the unit were carried out. . The joint and bellows functioned properly and were leak-tight. Corrosion of stainless steel in 0.04 m UO2SO4 containing equimolar beryllium sulfate was not greater at 10-15 fps and much less at 15-75 fps, than in HRT solution at 200 and 225 C. Increasing the beryllium sulfate concentration to 0.08 m increased corrosion at 225 C and resulted in an unstable solution at 300 C.
Date:
April 30, 1957
Creator:
Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Object Type:
Report
System:
The UNT Digital Library
Curve Plotting Routine for the Oracle
A general program has been written to plot curves on the Oracle curve plotter. A description of the code and complete instructions for preparation of input tapes and operation of the code are given. The code tape is available from the Mathematics Panel or from the author.
Date:
April 11, 1957
Creator:
Lietzke, M. P.
Object Type:
Report
System:
The UNT Digital Library
Supplement to: Curve Plotting Routine for the Oracle (57-4-56)
A general program has been written to plot curves on the Oracle curve plotter. The supplement includes changes to slow down some of the loops and minimize the possibility of read-around errors and changes to handle special cases.
Date:
October 22, 1957
Creator:
Lietzke, M. P.
Object Type:
Report
System:
The UNT Digital Library
Temperature Effects on the Measurement of Aqueous Liquid Level by the Differential Pressure Method and Recommendations for Placement of Taps on the HRT Replacement Heat Exchanger
Increasing temperature in an aqueous liquid system results in a decrease in liquid density and an increase in vapor density. When level is measured by the differential pressure method, temperature increase results in a decrease in the effective span f the instrument and a shift in zero. When the instrument reference leg is uncompensated, both zero and span shifts occur with the effects being most pronounced at the high levels. When the reference leg is compensated, zero shifts are eliminated (instrument zero is at 100% level for this type installation). For control purposes at levels above 50% of full level, the compensated reference leg installation will give the best results. For measurement of levels below 50%, the uncompensated installation is best. As errors in level indications will be produced, in either type installation, by temperature, pressure and steam withdrawal (power) effects, the placement of taps should be such as to place the normal or control level in the region of 50% indicated level.
Date:
April 26, 1957
Creator:
Moore, R. L.
Object Type:
Report
System:
The UNT Digital Library
The Choice in Thorium Oxide Slurries for the Prevention of Caking in Circulating Systems
A qualitative theory for cake formation in ThO2 slurries is presented. The sphere formation which occurs in "Standard" slurry can be explained on the same basis. The irregular and unpredictable yield strength is easily fitted into the theory. On the basis of this theory, the writer has been led to the conclusion that only colloidally stable slurries, or slurries with crystallites or comminution-resistant particles which are large enough to overcome colloidal effects (probably larger than 0.1u) can be used with assurance in the ThO2 reactor system. This conclusion holds for 300 gm/kg slurries as well as for more concentrated mixtures.
Date:
April 22, 1957
Creator:
Lyon, R. N.
Object Type:
Report
System:
The UNT Digital Library
Possible Radiation Damage to the Stator Windings of the HRT Circulating Pump
A study of the degree and effects of radiation damage to the motor winding of the HRT 400-! canned motor circulating pumps was made. With the gamma flux estimate and the available radiation damage data, the effective life of the stator windings was estimated to be about one year, for normal operation of the pump and motor.
Date:
April 80, 1957
Creator:
Gift, E. H.
Object Type:
Report
System:
The UNT Digital Library
Compendium of Experimental Results of the Circulation of Aqueous Thorium Oxide Slurries in Toxoids
Data are presented for all toroid runs which circulated aqueous thorium oxide slurries between Aug, 1054, and October, 1956. In addition, a tabulation of the properties of numerous thoria preparations is presented.
Date:
April 30, 1957
Creator:
Moore, G. E.; Benson, R. F.; McDaniel, F. E. & Wheeler, S. H.
Object Type:
Report
System:
The UNT Digital Library
Report of Slurry Blanket Test Run SM-2
Run SM-2 was run to determine whether a sulfated ThO2 slurry could be handled in a hydrodynamic system similar to the HRT test blanket. It was found that the ThO2 concentration circulating in the pipes was consistently 50% or less of the expected concentration based on the quantity of the oxide changed. The run lasted 1730 hours. It was terminated because of a slurry leak a few days before a shutdown had been scheduled. Severe erosion was found in the pump impeller and flow nozzle . Chloride concentration high enough to cause concern over possible stress corrosion cracking occurred on several occasions in the pressurizer.
Date:
April 29, 1957
Creator:
Parsly, L. J., Jr.; Falkenberry, H. L. & Miller, I. M.
Object Type:
Report
System:
The UNT Digital Library
Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study
The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2-3 µ. High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al2O3 and in theory would serve as a satisfactory second phase.
Date:
December 27, 1960
Creator:
King, Blake
Object Type:
Report
System:
The UNT Digital Library
ORR Startup Accident and Cooling Flow Coastdown Analog Analysis
Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is increased to the point where the level scram must be set above 50 Mw).
Date:
January 4, 1961
Creator:
Stone, R. S. & Colomb, A. L.
Object Type:
Report
System:
The UNT Digital Library
Water Treatment in Aqueous Homogeneous Reactors, Experience in HRE-2
A method for water treatment has been developed for corrosion protection in the steam-water cycle of Homogeneous Reactor Experiment No. 2. The use of potassium phosphates for pH control, hydrazine for oxygen removal, and limitation of chlorides in the boiler water to less than 1 ppm has resulted in trouble-free operation of the steam system from December 1957 to December 1960.
Date:
January 4, 1961
Creator:
Neumann, P. D.
Object Type:
Report
System:
The UNT Digital Library
Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop
Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same proportion in the temperature range of 330 to 365°C. Corrosion of titanium and Zircaloy-2 specimens was insignificant during the relatively short exposure periods.
Date:
January 6, 1961
Creator:
Griess, J. C.; Baker, J. M. & Savage, H. C.
Object Type:
Report
System:
The UNT Digital Library
Bremsstrahlung Absorption Measurements from Sr^90 TiO3
The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date:
January 13, 1961
Creator:
Butler, T. A. & Pierce, E. E.
Object Type:
Report
System:
The UNT Digital Library
Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960
A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date:
January 11, 1961
Creator:
Sadowski, G. S.
Object Type:
Report
System:
The UNT Digital Library
Revised Version of HFIR Critical Experiment-2 (HFCE-2)
A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date:
January 16, 1961
Creator:
Kasten, P. R. & Cheverton, R. D.
Object Type:
Report
System:
The UNT Digital Library
Some Heat Transfer Characteristics of ORR Fuel Elements
Analyses are generally made at the ORR with a view toward determining the surface temperatures of fuel plates.
Date:
January 19, 1961
Creator:
Wett, J. F., Jr.
Object Type:
Report
System:
The UNT Digital Library
Sources and Availability of Helium
A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date:
January 19, 1961
Creator:
Fraas, A. P.
Object Type:
Report
System:
The UNT Digital Library
Xenon and Samarium Poisoning
The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.
Date:
January 23, 1961
Creator:
Carlsmith, R. S.
Object Type:
Report
System:
The UNT Digital Library
A Useful Solution for Short Cylindrical Shells and Other Applications
The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.
Date:
February 14, 1961
Creator:
Moore, S. E.
Object Type:
Report
System:
The UNT Digital Library
Pressure Vessel Exposure to Fast Neutrons
In a gas-cooled reactor operating at very high power density the thickness of the reflector may be determine by the requirement that the steel pressure vessel be protected from an excessive dose of fast neutrons, rather than by the usual requirements of neutron economy and power distribution. It is important the the reflector not be made thicker than necessary, since an increase in pressure vessel diameter can result in a marked increase in cost, as well as a decrease in the permitted gas pressure level.
Date:
January 21, 1960
Creator:
Carlsmith, R. S.
Object Type:
Report
System:
The UNT Digital Library