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Quarterly Report of the Solution Corrosion Group for the Period Ending April 30, 1957

Description: 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. … more
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.
Item Type: Refine your search to only Report
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Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957

Description: A second test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel has been completed. The joint and bellows have now received 104 thermal cycles and 148 mechanical deflections. The joint and bellows have functioned properly; corrosion damage has been negligible, except for a small area on the bellows which has undergone pitting attack. Long-term runs with uranyl sulfate solutions of the concentration proposed or use in the HRT have shown the soluti… more
Date: January 31, 1957
Creator: Griess, J. C. F.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Item Type: Refine your search to only Report
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Radiation Dose Received by Passengers and Crew on Planes Carrying the Maximum Number of Radiation Units

Description: The dose of ionizing radiation received by passengers and crew members traveling on commercial airlines which transport radioisotopes is of interest to all persons who travel the airways frequently. Tariff regulations permit the air transport of 40 units of radioactive materials where one unit represents a quantity of radioisotopes which when packaged delivers a dose rate of one mr/hr at a distance of one meter from the center of the package. Using five different types of commercial aircraft, s… more
Date: March 1, 1957
Creator: Davis, D. M.; Hart, J. C. & Warden, A. D.
Item Type: Refine your search to only Report
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Radiation Level in the Stator Region of the HRT Fuel Circulation Pump

Description: The gamma dose rate in the motor region of the HRT fuel circulation pump was measured with the pump scroll full of radioactive solution. Extrapolation of the data to the solution activity expected in the pump under normal operation gives a dose rate well below that which would result in excessive gas production in the stator can within the life of the pump. The above dose rate does not include the effects of fast neutrons from the fuel solution or of the general cell radiation level in the vici… more
Date: July 3, 1957
Creator: Engel, J. R.
Item Type: Refine your search to only Report
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Radioactive Waste Disposal and Miscellaneous Work : Annual Report for Calendar Year 1956

Description: An annual report is given on the operation and costs of waste-disposal facilities at ORNL laboratories and operating buildings in the Bethel Valley area. The operations of the hot-chemical and metal-waste systems, the process-waste system, and the radioactive-gas-disposal system which utilized the 250-ft stack located in the Radioisotope area are discussed. The miscellaneous operations which include the SS (source and special nuclear) material control, SS material recovery, off-shift service fo… more
Date: September 11, 1957
Creator: Seagren, H. E. & Witkowski, E. J.
Item Type: Refine your search to only Report
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The Reaction of Zirconium with Uranium Dioxide

Description: An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date: June 11, 1957
Creator: Robinson, M. T.
Item Type: Refine your search to only Report
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Reactor Irradiation of Thorium and Uranium Oxides Slurries

Description: Thorium and thorium-uranium oxide slurries were irradiation in the Low Intensity Test Reactor (LITR) at temperatures up to 300C in small stirred autoclaves. Stirring was accomplished by means of an electromagnetically operated lunger. Stirrer operations was monitored suing an oscilloscope. Relative slurry viscosities were determined both in and out-of-pile using calibration curves of apparent viscosity versus stirrer rise time. Post-irradiation examination of selected slurries indicated no gros… more
Date: January 29, 1957
Creator: Krohn, N. A. & McBride, J. P.
Item Type: Refine your search to only Report
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The Relationship of Aqueous ThO2 Slurry Physical Properties of the Engineering Design of a Reactor System

Description: In a reactor system the principal components affect by slurry properties are the blanket vessel, pressurizer, heat exchanger, and dump tant. The particular properties that affect the operation of these components are: caking, degree of flocculation, foaming, and slime formation. these properties are related to the characteristics of compounds in a reactor system through experience gained in the operation of slurry loops. It is pointed out that the optimum slurry for one component may not necess… more
Date: June 17, 1957
Creator: Thomas, D. G.
Item Type: Refine your search to only Report
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Report of Slurry Blanket Test Run SM-2

Description: 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 co… more
Date: April 29, 1957
Creator: Parsly, L. J., Jr.; Falkenberry, H. L. & Miller, I. M.
Item Type: Refine your search to only Report
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Second and Third Operating Test of HRT Core Vessel Transition Joint and Expansion Bellows Mockup

Description: 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 transiti… more
Date: April 30, 1957
Creator: Greeley, R. S.; Ulrich, W. C.; Savage, H. C.; Griess, J. C. & Mauney, T. H.
Item Type: Refine your search to only Report
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Section 9.0 to Status Report on the Disposal of Radioactive Wastes

Description: Section 9.0 is the "Chemical Processes for Fission Product Concentration, Removal or Fixation" section of the Status Report on the Disposal of Radioactive Wastes. The report is divided into four areas: (1) Introduction; (2) Summary of waste processes; (3) Concept of a multipurpose waste processing facility; and (4) Details of some of the waste processes.
Date: September 3, 1957
Creator: Culler, Floyd L., Jr.
Item Type: Refine your search to only Report
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Semipermanent Freeze Plug Tests for HRT-CP

Description: Five uninsulated semipermanent freeze coils, series connected, can be frozen when submerged in 70 F water with a Freon-11 flow rate of 1.85 gpm at an inlet temperature of -40 F. The refrigeration unit of the HRT-CP is capable of delivering >3 gpm to a similar semipermanent freeze coil system located in Cell C. Therefore the number of F-11 risers required in Cell C of the HRT-CP can be minimized by series connecting this many semipermanent freeze coils where required.
Date: March 11, 1957
Creator: Winget, R. H.
Item Type: Refine your search to only Report
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The Sodium Hydroxide - Sodium Hydride System

Description: Portions of the NaOH-NaH phase diagram were studied by means of differential thermal analysis. Under certain conditions NaH will either react with NaOH according to the equation NaH + NaOH in equilibrium Na/sub 2/O + H/ sub 2/ or thermally dissociate according to the equation NaH in equilibrium Na + 1/2 H/sub 2/. Both of these reactions are suppressed by a high H/sub 2/ pressure; and NaH neither reacts nor dissociates to an extent sufficient to affect the results reported. This was evidenced by… more
Date: March 7, 1957
Creator: Kerzner, Marvin S.; Kelly, Henry C. & Johnson, Sidney
Item Type: Refine your search to only Report
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The Sodium Hydroxide - Sodium Oxide - Sodium - Sodium Hydride - Hydrogen System

Description: Sodium hydride dissolves in and reacts with molten NaOH to give an equilibrium mixture of NaH, NaOH, Na/sub 2/O, Na, and H. In the case where there is a gaseous phase (hydrogen) and only one condensed phase, the system is defined by the temperature, pressure, and one composition variable. The equilibrium, H/ sub 2/ pressure, which is a measure of the H/sub 2/ activity within the melt, was determined as a function of the composition of the condensed phase(s) at 600, 700, and 500 deg for equilibr… more
Date: March 7, 1957
Creator: Kelly, Henry C.; Sullivan, Edward A. & Johnson, Sidney
Item Type: Refine your search to only Report
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Source of Fission Products in LITR Cooling Water

Description: A study has been made of the radioactive nuclides present in the cooling water of the Low Intensity Test Reactor. Prominent nuclides which have been identified include Np239 and certain fission products. The experimental evidence points to the probability that there could be adequate U235 contamination on the fuel plates to quantitatively account for the fission products identified in the LITR cooling water. inasmuch as new aluminum does not contain uranium, it must be assumed that the contamin… more
Date: March 26, 1957
Creator: Moeller, D. W. (Dade W.) & Leddicotte, G. W.
Item Type: Refine your search to only Report
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Spectrographic Analysis of Normal Human Tissue from Dallas, Texas

Description: All tissues included in this report were received from Dallas, Texas and were collected, ashed and analyzed according to the methods described in ORNL-CF-57-2-2. The average value of the concentration for each element in a tissue is the average of the concentrations in only those samples of the tissue which contained the element. For example, if, of 25 lives analyzed, only 10 contained lead, the average for lead in liver is the average of those 10 values. For those tissues in which an element d… more
Date: February 26, 1957
Creator: Tipton, I. H.; Cook, M. J.; Steiner, R. L.; Foland, J. M.; McDaniel, K. K. & Fentress, S. D.
Item Type: Refine your search to only Report
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Spectrographic Analysis of Normal Human Tissue from Miami, Florida

Description: All tissues included in this report were received from Miami, Florida and the majority are from Jackson memorial Hospital. They were collected, ashed and analyzed according to the methods described in ORNL-CF-57-2-2. The average value of the concentration for each element in a tissue is the average of the concentrations in only those samples of the tissue which contained the element. For example, if, of 25 lives analyzed, only 10 contained lead, the average for lead in liver is the average of t… more
Date: February 28, 1957
Creator: Tipton, I. H.; Cook, M. J.; Steiner, R. L.; Foland, J. M. & McDaniel, K. K.
Item Type: Refine your search to only Report
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Spectrophotometric Determination of Cerium with Tiron

Description: A spectrophotometric method for the determination of cerium with Tiron (disodium-1,2-dihydroxybenzene-3,5disulfonate) was applied to the determination of cerium in samples which contain uranium and zirconium. The cerium-Tiron complex in solutions of pH 8 or greater exhibits an absorption maximum of 500 mu . This reagent does not react with any other lanthanide element. The interference of iron, uranium, and zirconium was eliminated by extracting these interfering elements with a solution of tri… more
Date: June 14, 1957
Creator: McDowell, B. L.; Meyer, A. S., Jr. & White, J. C.
Item Type: Refine your search to only Report
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Status Report on the Disposal of Radioactive Wastes

Description: The new and as yet unsolved problems introduced by the production of large quantities of fission products and radioactive isotopes from fission or neutron capture present mankind a most complex technical, economic, and political problem. On one hand, the possibility of using the fission process to produce energy from an unexploited and abundant natural source is emerging from large programs of research and development. We are also beginning to see the promise of use of particulate and electroma… more
Date: June 25, 1957
Creator: Culler, Floyd L., Jr. & McLain, Stuart
Item Type: Refine your search to only Report
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Stress-Corrosion Cracking Problems in the Homogeneous Reactor Test

Description: Chloride-induced stress-corrosion cracking has been encountered in the Homogeneous Reactor Test during the preliminary testing. The rector is constructed of austenitic stainless steels. It is unique in that it will operate at 250 to 300 C with an aqueous uranyl sulfate solution fuel containing 200 to 500 ppm of dissolved oxygen. The cracking has occurred in a secondary system used for detecting leaks in the flanged joints of the primary systems and in the grooves of flanges in the primary syste… more
Date: January 31, 1957
Creator: Bohlmann, E. G. & Adamson, G. M.
Item Type: Refine your search to only Report
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