Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19) (open access)

Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19)

The apparatus and procedures that are to be used to fill the liquid metal system of the Pratt and Whitney Forced Convection Liquid Metal Inpile Loop are described. The liquid metal to be used is a mixture containing 56% Na and 44% K, which is a liquid at room temperature. In order to simplify the filling procedure at the reactor site, two containers, each of which contains exactly enough liquid metal to fill the experiment to the prescribed level, a fill dolly incorporating a purified helium system, and an evacuation system will be provided at the reactor site. After completion of the liquid metal transfer, the liquid metal fill tube will be crimped, cut, and seal welded. The liquid metal and helium systems will then be pressurized through the helium fill tubes, which will also be crimped, cut, and seal welded. Each tube seal weld will be inspected after completion of the weld by mass spectrometry leak check and dye penetrant fault detection
Date: April 29, 1959
Creator: Heyl, P. T.
System: The UNT Digital Library
Braze Alloys v.s. Atmospheres : Final Report Project 1325 (open access)

Braze Alloys v.s. Atmospheres : Final Report Project 1325

Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, sufficient cleaning action might be attoined without the inherent hazards encountered with hydrogen. An investigation of the argon - 2 1/2% hydrogen gas as a brazing atomosphoer
Date: May 21, 1959
Creator: Rogers, S. L.
System: The UNT Digital Library
Survey: Oxidation Characteristics of Columbium and Columbium Base Alloys (open access)

Survey: Oxidation Characteristics of Columbium and Columbium Base Alloys

Unclassified experimental data concerned with the oxidation characteristics of Nb and Nb-base alloys are presented. The bulk of the results is presented in tabular form and cataloged under laboratory name sub-headings. The theory of alloy development for oxidation resistance is discussed. Methods of evaluating oxidation behavior are outlined.
Date: May 20, 1959
Creator: Clough, W. R. (William Raymond); Hirakis, E. C. & Krutenat, R. C.
System: The UNT Digital Library
Weldability of Hayes Alloy #25 (open access)

Weldability of Hayes Alloy #25

Technical report describing the process to determine the fusion welding characteristics of Haynes Alloy #25 as applied to TLJ-100530, Corrosion Loops. Hayes Stellite Alloy #25 is a cobalt-base alloy for corrosion resistant high temperature applications. This material, when welded by the inert gas shielded tungsten arc method, produces sound ductile joints. Material thicknesses greater than 12 gauge require standard joint preparations, a V joint being preferred up to 1/4 inch and a U joint for greater thicknesses. Welding heat should be kept to a minimum followed by fast cooling. The molten metal is very fluid and may present difficulties when position welding.
Date: May 19, 1959
Creator: Rogers, S. L.
System: The UNT Digital Library
Braze Ring Mold for Sintering & Casting (open access)

Braze Ring Mold for Sintering & Casting

Technical report of an investigation to determine a suitable material for sintering and casting of braze rings. Braze rings afford an excellent means of preplacing braze alloy on tube to head joints of radiators, heat exchangers, and similar applications. A cast ring is especially desirable because of its increased strength. Previous efforts at casting had used welding grade carbon blocks with the desired ring cavities machined into their surface. Conclusion: Stackpole grade 331 electro-graphite provided the best results of the materials investigation. It is hard and more readily machinable with conventional tools than other grades. Carbon, in general, proved to be more satisfactory especially due its ease and speed of fabrication.
Date: May 14, 1959
Creator: Rogers, S. L.
System: The UNT Digital Library
Bonding of Tantalum (open access)

Bonding of Tantalum

Technical report describing the investigation undertaken to determine the necessary requirements for obtaining sound bonded joints on tantalum. Corrosion and Mass Transfer Loops LTTN 237A and 427 called for fabrication of 430 stainless steel clad tantalum tubing. Since there was little or no experience at welding this material at CANEL, specimens were welded using vacuum chambers and plastic chambers as normally used for loop fabrication. Resistance welding was performed without the use of a special atmosphere producing sound bonds.
Date: June 17, 1959
Creator: Rogers, S. L.
System: The UNT Digital Library
Diffusion of Xenon in Columbium (open access)

Diffusion of Xenon in Columbium

The diffusion coefficient was calculated for the diffusion of Xe through Nb and found to be 0.064 exp (-18,600/RT).
Date: November 20, 1959
Creator: Gregory, D. P. (Derek P.) & Leavenworth, H. W. (Howard W.)
System: The UNT Digital Library
Producibility of an Alloy of Columbium with One Percent Zirconium (open access)

Producibility of an Alloy of Columbium with One Percent Zirconium

Abstract. Proven mineral resources show that niobium is the most abundant of the refractory metals and extraction capacity is adequate to meet foreseeable requirements. Approximately four tons of Nb-1% Zr alloy were melted, forged, drawn, and rolled to produce various mill forms and relatively large die impression forgings. It was demonstrated that the Nb-1% Zr alloy is readily amenable to melting, primary working, and secondary working using standard equipment available in the specialty steel and nickel alloy industries. In general, the hot malleability of the alloy is significantly better than that of the more refractory nickel base high temperature alloys and is comparable to the stainless steels. Methods were successfully developed to protect the alloy against contamination during hot working. Cold fabricability proved to be outstanding. Reductions up to 90% were achieved during cold rolling of sheet with no intermediate stress relief or annealing treatment. Tube drawing reductions up to 50% were normal with no intermediate annealing. Over-all, the cold workability of this alloy was superior to that of the stainless steels. There was no problem of embrittlement over the full range of working temperatures which were used during the course of this work, namely from room temperature to 2350 …
Date: December 9, 1959
Creator: Raring, L M
System: The UNT Digital Library
Evaluation of Commercial Ceramic Coating for Short Time Protection of Columbium 1% Zirconium (open access)

Evaluation of Commercial Ceramic Coating for Short Time Protection of Columbium 1% Zirconium

Abstract. Fourteen commercial enamel frits from five different manufacturers were tested to determine their abilities to protect Nb-1% Zr during the forging cycle in the temperature range of 1800 to 2300 deg F. One frit was found to afford good coverage and protection at 2200 deg F at times up to 5 hours of exposure. Adherence was excellent during upset forging of a coated Nb--1% Zr sample heated 45 minutes at 2200 deg F. Another frit afforded good protection and coverage at 1700 deg F. (auth)
Date: October 10, 1960
Creator: McGrath, D. W.
System: The UNT Digital Library
An Analysis of Inconsistencies in Removal Cross Sections of Carbon and Oxygen (open access)

An Analysis of Inconsistencies in Removal Cross Sections of Carbon and Oxygen

Abstract. Some recent analysis of certain Lid Tank fast neutron dose rates measured in oil and water indicates that there are some basic inconsistencies with reported oxygen and carbon removal cross sections and the reported data. These inconsistencies may be explained in several ways: (1) The reported carbon removal cross section is wrong. (2) The reported oil composition is wrong. (3) The reported oxygen removal cross section is wrong since it is based on an assumed rather than a measured oil composition. (4) Some of the experimental data are wrong. It is not possible to determine which of the above is most likely on the basis of analysis alone but the possibilities are pointed out and, based on the assumption that all the experimental data are correct, it appears most likely that the oil composition assumed in ORNL 2197 was in error.
Date: January 20, 1961
Creator: {{{name}}}
System: The UNT Digital Library
Spinning of Columbium & Columbium 1%- Zirconium Tubing (open access)

Spinning of Columbium & Columbium 1%- Zirconium Tubing

The following objectives were planned for this project. (1) Development of spinning data necessary for spinning Columbium and Columbium-1% Zirconium tubing from ingot, forged or welded tube blanks. (2) Determine mechanical & metallurgical properties of spun Columbium and Columbium-1% Zirconium tubing. (3) Determine dimensional and tolerance limits possible to attain on spun Columbium and Columbium-1% Zirconium tubing based on our present equipment, tooling limitations, and the spinning tests performed for objective No. 1.
Date: January 19, 1961
Creator: Barker, Wharton R.
System: The UNT Digital Library
Refractory Metals as Alkali Liquid Metal Containment Materials (open access)

Refractory Metals as Alkali Liquid Metal Containment Materials

Abstract. Refractory metals and their alloys are good container materials for alkali metal coolants. Thermodynamics of interaction with contaminants have been correlated with experimental test and show the need for high purity materials. Structural metal solubility data to 1600F can be used to correlate and predict engineering systems.
Date: June 15, 1962
Creator: Cleary, Robert E., 1920-
System: The UNT Digital Library
Design Criteria for Lithium-Cooled Reactor Experiment (LCRE) at NRTS (open access)

Design Criteria for Lithium-Cooled Reactor Experiment (LCRE) at NRTS

This technical report provides design criteria for reactor test facilities utilizing existing structures at the former ANP area of the National Reactor Testing Station (NRTS) near Idaho Falls, Idaho. The information and specifications presented establish the basis for the design of facilities providing the capability for installation, extended nuclear testing and remote disassembly of the 10mw Lithium-Cooled Reactor Experiment (LCRE). Facility structural and process design has been developed to the extent required to assure the safety and technical feasibility of the proposed facilities for reactor operation.
Date: September 4, 1962
Creator: Hedden, D. T.
System: The UNT Digital Library
Alkali Metal Physical Properties Program at Pratt & Whitney Aircraft-CANEL (open access)

Alkali Metal Physical Properties Program at Pratt & Whitney Aircraft-CANEL

The favorable combination of physical properties such as heat capacity, viscosity, electrical resistivity, thermal conductivity and high temperature liquid range make alkali metals, in principle, among the best heat transfer fluids available for use in nuclear reactor and other esoteric powerplant systems. Unfortunately, many of these properties are not known with sufficient certainty in the high temperature region to permit optimization of design criteria for developing maximum efficiency coolant systems. For this reason, Pratt & Whitney Aircraft-CANEL, have been concerned for some time in extending the physical properties data of alkali liquid metals in the high temperature region. A supplemental program is being initiated to study some of the properties of alkali metals in the gas phase. This information is required for designing systems where the alkali vapor is the working fluid. In addition, programs are under way to study the solubility of noble gases in alkali liquid metals and wetting characteristics of these liquid metals with structural materials.
Date: June 15, 1962
Creator: Kapelner, S. M. & Cleary, Robert E., 1920-
System: The UNT Digital Library
Design Criteria for Reactor Test Support Facility at NRTS (open access)

Design Criteria for Reactor Test Support Facility at NRTS

This technical report provides a design criteria for a technical support facility for the Lithium Cooled Reactor Experiment (LCRE) and SNAP-50-DR-1 Test Facilities. The support facility is adjacent to the LCRE Test Facility and is located completely within the existing Building 629 structure at the former ANP area of the National Reactor Testing Station (NRTS) near Idaho Falls, Idaho. The information and specifications presented establish the basis for the design of laboratories, shops and engineering areas required to support the installation, operation, maintenance and disassembly of the LCRE and SNAP-50 tests. The construction and modification required to adapt the building to reactor test support operations are described in detail in the following report.
Date: September 14, 1962
Creator: Macfarlane, D. B.
System: The UNT Digital Library
The Thermal Expansion of Five Titanium Carbide Cermets from 68 to 1800F (open access)

The Thermal Expansion of Five Titanium Carbide Cermets from 68 to 1800F

This technical report presents measurements of the thermal expansion of five titanium carbide type cermets from 68 to 1800F. These cermets are designated by Kennametal, Inc., as K 138A, K 150A, K 152B and K 162B. They contain from 64 to 80 weight percent titanium carbide, 10 to 30 weight percent metal binder and 6 to 10 weight percent other carbides. The metal binders are cobalt, nickel, and nickel and molybdenum. An attempt was made to calculate the thermal expansion of each type cermet from thermal expansions of the constituents. The expansion of the mixture was computed by weighting and expansions of the constituents according to (1) weight percent of the constituents, (2) volume percent of the constituents and (3) according to a value developed for mixtures by P. S. Turner. It was found that expansions computed according to volume percent and by Turner's method agreed with measured values with +- 5 percent. The values calculated by weight percent were from 5 to 11 percent higher than the observed values. The thermal expansions of these cermets are compared with the expansions of a group of metals and alloys.
Date: August 17, 1962
Creator: Harrington, L. C. & Rowe, G. H.
System: The UNT Digital Library
High Voltage Electron Beam Welding of W-RE Thermocouples (open access)

High Voltage Electron Beam Welding of W-RE Thermocouples

A series of W-5 Re/W-26 Re thermocouples have been electron beam welded at the Hamilton Standard Division at our request. This technical report is a summary of our evaluation of these joints. These weldments did exhibit incomplete fusion in cap welds and some porosity in undesirable lead junction shapes. In fairness, this was a single attempt to make a difficult joint, and the objective of ungrounded 1/16 OD clad joints was met. As noted by Hamilton, two changes are necessary to improve this joint design: (1) swaging to forming the clad end rather than crimping prior to cap welding. (2) using a fixture with rotary motion on a tilting axis.
Date: December 13, 1962
Creator: Doyle, J.
System: The UNT Digital Library
Engineering Report on the Design of the Pratt & Whitney Aircraft Forced Convection Alkali Metal Vaporization Condensation Heat Transfer Rig (open access)

Engineering Report on the Design of the Pratt & Whitney Aircraft Forced Convection Alkali Metal Vaporization Condensation Heat Transfer Rig

Summary. A test rig has been designed to obtain basic two phase forced convection liquid metal heat transfer and pressure drop data for use in the design of liquid metal boilers. This engineering report includes background of the boiling problem, partial summary of work done by other investigators, the object, scope, engineering, and operations of this test rig, and a summary of reproducibility tests conducted in a water back-up rig.
Date: January 18, 1963
Creator: Bernstein, E.
System: The UNT Digital Library
Short Time Strength Data for CS 1830 Series Cb-1Zr, Annealed at 2200F (open access)

Short Time Strength Data for CS 1830 Series Cb-1Zr, Annealed at 2200F

This technical report is a summary of short time strength data for CS1830 series Cb-1Zr material. The data are presented as a function of fabrication history or the amount of cold work received during fabrication. Three fabrication categories were considered for comparison: forgings and extrusions; bar, plate, rod and pipe; and sheet and tubing. Forgings and extrusions having received no cold work showed the highest strength over the entire temperature range 68F to 2800F; bar, plate, rod and pipe received moderate cold work and showed lower strength than forgings and extrusions but higher strength than sheet and tubing in the temperature range 2000F to 2800F.
Date: February 8, 1963
Creator: Watson, W. L.
System: The UNT Digital Library
The Thermal Expansion of Thirteen Tungsten Carbide Cermets from 68 to 1800 F (open access)

The Thermal Expansion of Thirteen Tungsten Carbide Cermets from 68 to 1800 F

The linear thermal expansion of thirteen tungsten carbide cermets with cobalt binder was investigated experimentally over the temperature range from 68 to 1800 F. Cobalt contents varied from 2.5 to 60 per cent. Several compositions included additions of mixed carbides of titanium, tantalum, and columbium. The experimentally observed coefficients of thermal expansion for the various compositions were compared with coefficients analytically computed from the coefficients for the constituents. Three such analytical methods were evaluated. In one method, the coefficient of expansion of the mixture was computed by volume fractions and in a second method by weight fractions. In the third method, the computation accounted for the stresses set up in the mixture by the difference in thermal expansion of the carbide skeleton and the cobalt binder. The expansions of all these cermets agreed with the values computed by weight fractions or by the stress method within 12 per cent, and by volume fractions within 28 per cent. The cermets containing less than one per cent mixed carbides agreed with the expansion computed either by weight fractions or by stress within 8 per cent, the cermets containing more than five per cent mixed carbides agreed with values computed by volume fractions …
Date: April 26, 1963
Creator: Harrington, L. C. & Rowe, G. H.
System: The UNT Digital Library
The Thermal Decomposition of Uranium Mononitride (open access)

The Thermal Decomposition of Uranium Mononitride

The use of uranium mononitride as a nuclear fuel is being considered for a number of high temperature applications. In comparison with the most often applied high temperature fuels, UO2 and UC, one finds that UN has a combination of the high melting point of UO2 and the thermal conductivity and high uranium density of UC. However, interest in UN is often dampened by qualitative indications of its low thermal stability and by lack of experimental thermodynamic data. Is is the purpose of this study, therefore, to provide a quantitative measure of the thermal stability of UN and to establish some of its thermodynamic properties.
Date: January 7, 1964
Creator: Vozzella, P. A.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
System: The UNT Digital Library
The Thermal Conductivity of Uranium Monocarbide (open access)

The Thermal Conductivity of Uranium Monocarbide

Uranium carbide shows promise as a fuel material for reactors operating at relatively high temperatures based on its high melting point, high uranium density and high thermal conductivity. Before refined reactor designs can be made, however, good quantitative data on the thermal conductivity at temperatures in excess of 1000C is required. This technical report presents data gathered as part of a continuing study aimed at determining the thermal conductivity of refractory uranium fuels as a function of temperature, density and composition over the temperature range 1000-2200C. At the inception of this program it was felt that an absolute method capable of achieving high temperatures was necessary and that the difficulties encountered in fabricating the large complex specimens needed were justified. The steady state radial heat flow method and apparatus of Rasor and McClelland were therefore chosen. The technical report discusses the experimental equipment and presents results of measurements on three specimens of UC over a temperature range 900 to 1600C. An analysis of the data is made with respect to other physical properties of the material and the measured conductivities are compared with the work of other investigators.
Date: April 2, 1964
Creator: Sobon, J. T.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
System: The UNT Digital Library
Purification of Argon, Helium and Xenon : a Bibliography (open access)

Purification of Argon, Helium and Xenon : a Bibliography

This bibliography contains 145 references on the technology and apparatus used in the purification of argon, helium and xenon, and on the analysis for water, carbon monoxide, hydrogen, nitrogen, and oxygen, in the purification process. The references are arranged in four classifications: general, argon, helium, and xenon. Within each classification, the references are arranged in chronological order.
Date: September 16, 1956
Creator: Cernak, Elizabeth A.
System: The UNT Digital Library
Self-Shielding Cross Sections : a Bibliography (open access)

Self-Shielding Cross Sections : a Bibliography

This bibliography contains 37 references on self-shielding cross sections. The bibliography is limited to the period from 1951 through November 1959 with the references arranged alphabetically by title. The sources used in compiling this bibliography were: Abstracts of Classified Reports Nuclear Science Abstracts
Date: December 29, 1959
Creator: Cernak, Elizabeth A.
System: The UNT Digital Library