Heat Exchanger Design Charts (open access)

Heat Exchanger Design Charts

From introduction: "The ORNL-ANP liquid-to-liquid heat exchanger design and development effort has been based on an exceptionally high performance matrix of closely-spaced small diameter tubes that permits practically pure counter-flow operation. In the course of full-scale aircraft power plant design work a number of charts for this type of heat exchanger has been prepared. These charts were intended in part to show the effects of the various parameters in a readily understandable form, and in part to simplify and to reduce markedly the chore of making detailed design calculations. These charts have proved so helpful it seemed very worthwhile to assemble them into a report along with brief explanations and sample calculations."
Date: December 7, 1952
Creator: Fraas, A. P. & LaVerne, M. E.
System: The UNT Digital Library
Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952 (open access)

Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."
Date: March 7, 1957
Creator: Livingston, Robert S. & Howard, F. T.
System: The UNT Digital Library
Evaluation of Tributyl Phosphate in Jet Mixing Columns as a Solvent for Uranium Extraction From Slurry-Type Ore Feeds (open access)

Evaluation of Tributyl Phosphate in Jet Mixing Columns as a Solvent for Uranium Extraction From Slurry-Type Ore Feeds

Technical report outlining the physical operability of 30% tributyl phosphate in a hydrocarbon dilutent for the extraction of uranium from more feed slurries. Operability had been satisfactorily demonstrated in jet mixing columns at the pilot plant of the Mallinckrodt Chemical Works. [From Abstract]
Date: December 7, 1950
Creator: Runion, T. C. & Yeager, J. H.
System: The UNT Digital Library
A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man (open access)

A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man

In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.
Date: August 7, 1959
Creator: Sanders, Fred W.
System: The UNT Digital Library
Radiators for Space Power Plants (open access)

Radiators for Space Power Plants

An improved heat sink for space vehicles was proposed in ORNL-CF-59-1-21. Subsequent work on the problem has indicated that there is a substantial probability of a puncture of such a radiator by meteors. To meet this problem a modified geometry has been evolved for which the probability of a meteor puncture should be reduced by a factor of at least 100 relative to the radiator of the original proposal at the expense of an increase in radiator weight of possibly 30%. This memorandum outlines the approach to the problem and a series of similar promising solutions.
Date: August 7, 1959
Creator: Fraas, A. P.
System: The UNT Digital Library
The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates (open access)

The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates

Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after irradiation and after decay of the protactinium 233 was greater than before irradiation. A fuel element of this nature appears to offer excellent potentialities from the standpoint of radiation stability.
Date: September 7, 1955
Creator: Carrell, R. M.
System: The UNT Digital Library
ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report (open access)

ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report

This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.
Date: September 7, 1955
Creator: Matherne, J. L.; Brooksbank, R. K.; Campbell, D. O.; Chandler, J. M.; Rylton, C. D.; Leuse, R. E. et al.
System: The UNT Digital Library
Metallurgy of Thorium and Thorium Alloys Interim Report [for] July 1, 1949 to July 1, 1951 (open access)

Metallurgy of Thorium and Thorium Alloys Interim Report [for] July 1, 1949 to July 1, 1951

Technical report containing a comprehensive study of the physical metallurgy of thorium and some of its alloys containing additions of Be, Si, Zr, Ti, Al, Nb, Cr, Mn, and Ce. Melting range, fabricating characteristics, and tensile properties were studied. [From Abstract]
Date: December 7, 1951
Creator: Frye, J. H. & Hamby, D. E.
System: The UNT Digital Library
The Oak Ridge National Laboratory Research Reactor Safeguard Report (open access)

The Oak Ridge National Laboratory Research Reactor Safeguard Report

The proposed ORNL Research Reactor is designed to serve as a general purpose research tool delivering a maximum thermal flux of 8x10^13 n/cm2-sec at the initial power level of five megawatts. Operation at power levels up to ten megawatts is proposed for such items as sufficient cooling capacity is available to handle the increased heat load. The reactor will use MTR-type fuel elements and beryllium reflector pieces in a 7 x 9 grid with moderation and cooling provided by forced circulation of demineralized water. The reactor tanks are submerged in a barytes concrete pool, filled with water, which serves as a biological shield. Experimental facilities include two 18" diameter "Engineering Test Facilities" and six 6" diameter beam holes. In addition, access to the core is available through the water of the pool. The result on the surrounding population of release to the atmosphere of a large fraction of the radioactive material in the core has been computed by two methods. It is shown that under certain conditions off-area personnel could be subjected to greater than the maximum permissible exposure. An analysis of the maximum hazard caused by the release of the entire contents of the core to the local watershed …
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J. P.
System: The UNT Digital Library
Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1951 (open access)

Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1951

Technical report covering the metallurgy of thorium and on fabrication techniques. Report investigates the stability and corrosion resistance of thorium exposed to eutectic NaK, extrusion as a means of fabrication of thorium tubes or rods, and corrosion of large single metal crystals by liquid metals. [From Summary]
Date: June 7, 1951
Creator: Miller, E. C. & Bridges, W. H.
System: The UNT Digital Library
Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia (open access)

Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date: June 7, 1962
Creator: Kitts, F. G. & Clark, W. E.
System: The UNT Digital Library
Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2 (open access)

Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2

The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.
Date: April 7, 1960
Creator: Lees, E. A.; Boyle, R. F. & Spalaris, C. N.
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1952 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1952

This quarterly progress discusses the ongoing work at the Oak Ridge National Laboratory for the quarter ending in March 10, 1952. Topics discussed include reactor theory and design, shielding research, materials research, and includes appendixes with supplemental information.
Date: May 7, 1952
Creator: Briant, R. C.; Miller, A. J. & Cottrell, William B.
System: The UNT Digital Library
The Oak Ridge National Laboratory Research Reactor Safeguard Report (open access)

The Oak Ridge National Laboratory Research Reactor Safeguard Report

This memorandum sets forth a recommended uniform basis for designing the ORN shield.This includes design values for power level and emergent radiation, standards values for various material properties, and basic radiation intensities.
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J.P.
System: The UNT Digital Library
An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys (open access)

An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys

The fabrication of heat exchangers and radiators to be used in conjunction with high-temperature nuclear reactors may present exceedingly complex problems. Rigid heat transfer requirements may necessitate the use of compact assemblies of thin-walled small-diameter tubes as integral parts of the heat transfer units. Intricate designs may also be required in which cooling fins must be securely joined to the tubes at closely spaced intervals. In addition to the difficulties in fabrication imposed by the designs themselves, the high operating temperatures involved require the careful selection of materials and joining techniques. The choice of fabrication procedure for a given component must not only be based upon the stresses and temperatures to be encountered, but also upon special factors peculiar to nuclear service. Since many reactor applications employ highly corrosive environments, compatibility of the structural ma terials with the corrosive media is of paramount importance. The low nuclear cross-section require ment for brazing alloys to be used inside the re actor also places stringent limitations on the possible choices of in-pile applications. The use of boron in alloys for certain service may not be considered feasible, for example, because of its high nuclear absorption cross section. Although welding is used extensively …
Date: November 7, 1956
Creator: Hoffman, E. E.; Leitten, C. F., Jr.; Patriarca, P.; Slaughter, G. M.; Pope, J. E.; Shubert, C. E. et al.
System: The UNT Digital Library
Synthesis of Dimethyl Selenide (open access)

Synthesis of Dimethyl Selenide

The preparation of essentially pure dimethyl selenide for the Isotype Separations Group, Chemistry Division, is described. The compound was prepared by warming a mixture of selenium, sodium hydroxide, sodium formaldehyde sulfoxylate in aqueous solution for several hours at 50°C and then adding methyl iodide. Dimethyl selenide was removed by distillation.
Date: October 7, 1960
Creator: White, J. C.
System: The UNT Digital Library
Study of Dispersant Agents for Thorium Oxide (open access)

Study of Dispersant Agents for Thorium Oxide

A preliminary study of dispersing agents for thorium oxide has been completed and several of the dispersants have possible uses. Also many of the industrial dispersing agents tested are not usable with thorium oxide due to induced behavior causing balling and caking. The effects of nitric acid concentration have been observed to also effect each dispersing agent.
Date: August 7, 1959
Creator: Bate, L. C. & Leddicotte, G. W.
System: The UNT Digital Library
Effect of Pressure Differentials on Deflection of the Outer Fuel Plates of Brazed APPR Fuel Elements (open access)

Effect of Pressure Differentials on Deflection of the Outer Fuel Plates of Brazed APPR Fuel Elements

One of the considerations in designing a flat plate fuel element is the resistance of the fuel plates, especially the outer plates in the fuel plate array, to deflection and permanent deformation as a result of pressure differentials. An investigation was recently initiated wit the objective of obtaining preliminary information on the APPR-type fuel element to determine the effect of pressure differentials on the outer plates in the fuel assembly. The APPR-1 fuel element consists of 18 flat composite stainless steel fuel plates, joined to grooved 50 mil thick type 304L stainless steel side plates by brazing with Coast Metals N. P. alloy.
Date: February 7, 1957
Creator: Erwin, J. H. & Beaver, R. J.
System: The UNT Digital Library
Metallographic Examination of ORNL #1, SHE #2 (open access)

Metallographic Examination of ORNL #1, SHE #2

Small Heat Exchanger ORNL #1, type SHE #2, was removed form test stand B after 2071 hours of operation. Thirty-five samples were removed form the entire heat exchanger. The corrosion found on the outside of the tubes exposed to the fluoride mixture ranged to a maximum depth of .004 inches; however, the frequency of occurrence along the tube wall was heavier at the NaK outlet header, which was the hottest area in the heat exchanger. The depth of attack observed on the fluoride side of this heat exchanger was uniform from header to header and did not exceed .004 inches.
Date: February 7, 1957
Creator: VanCleve, J. E.; DeVan, J. H. & Crouse, R. S.
System: The UNT Digital Library
Operation of In-Pile Loop L-4-12 (open access)

Operation of In-Pile Loop L-4-12

Loop L-4-12 was the seventh corrosion test loop operated in HB-4 beam hole at the LITR. The loop was inserted on January 24, 1956, and removed on April 17, 1956. This loop had a titanium core which was attached to the 347 stainless steel loop with special titanium to stainless steel couplings.
Date: January 7, 1957
Creator: Walter, F. J.
System: The UNT Digital Library
The Helium Purification System for the Proposed 800 MWT Pebble Bed Reactor (open access)

The Helium Purification System for the Proposed 800 MWT Pebble Bed Reactor

A helium coolant purification system was designed for the proposed 800 MWT Pebble Bed Reactor. The purification system will operate on a coolant side stream with a flow rate 1% of the total coolant flow and there are provisions for radioactive and non-radioactive contamination removal.
Date: December 7, 1960
Creator: Scott, C. D. & Suddath, J. C.
System: The UNT Digital Library
The Sodium Hydroxide - Sodium Oxide - Sodium - Sodium Hydride - Hydrogen System (open access)

The Sodium Hydroxide - Sodium Oxide - Sodium - Sodium Hydride - Hydrogen System

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 equilibrium mixtures with original compositions of 2.5 to 97.5, 5.0 to 95.0, l0.0 to 90.0, and 20.0 to 50.0 mole% NaH-NaOH. The equilibrium H/sub 2/ pressure-composition isotherms obtained by removing measured increments of H/sub 2/ were reproduced by reabsorbing H/sub 2/. Results for the 5.0 mole % NaH mixture were duplicated by starting with an equivalent quantity of either Na in NaOH or Na/sub 2/O in NaOH, and reacting with measured increments of H/sub 2/. The system is discussed in relation to the interdependent reactions involved, the phase rule, the thermodynamics of certain reactions, and experimental techniques employed. (auth)
Date: March 7, 1957
Creator: Kelly, Henry C.; Sullivan, Edward A. & Johnson, Sidney
System: The UNT Digital Library
The Sodium Hydroxide - Sodium Hydride System (open access)

The Sodium Hydroxide - Sodium Hydride System

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 the fact that changing the H/ sub 2/ pressure above the system in the range indicated did not change, within the limit of error of the experiments ( approximately plus or minus 5 deg ), the temperature at which a phase change was started or completed. Therefore the concentrations of Na and Na/sub 2/O present in the samples must have been small in all cases. Under a high H/sub 2/ pressure, therefore, the system may be considered as essentially binary, consisting of NaOH and NaH. (auth)
Date: March 7, 1957
Creator: Kerzner, Marvin S.; Kelly, Henry C. & Johnson, Sidney
System: The UNT Digital Library
Volatility Pilot Plant : Design of a NaF Packed Tower for Removing HF from Fluorine (open access)

Volatility Pilot Plant : Design of a NaF Packed Tower for Removing HF from Fluorine

A 4-ft-7-in. adsorption column packed with 1/8 in. sodium fluoride pellets was designed to reduce the hydrogen fluoride content of the fluorine being used by the Volatility Pilot Plant from 5% to less than 0.01%. It will be a non-isothermal packed bed with the bas inlet heated to 100 C to avoid plugging and the exit cooed to 25 C for more complete HF removal.
Date: March 7, 1957
Creator: Watson, J. S.
System: The UNT Digital Library