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.

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.

This partially annotated bibliography contains references on boiling heat transfer of liquid metals. Emphasis is place on boiling heat transfer of liquid sodium, liquid potassium, and liquid rubidium. The period covered is 1950 to date. References are arranged alphabetically by title. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Nuclear Science Abstracts.

This bibliography contains 147 references on the fabrication of beryllium. References are also given on the brazing, casting, cladding, extrusion and welding of beryllium and some beryllium-rich alloys. The bibliography is limited to the period 1950 - 1959. references are arranged alphabetically by title, with author and subject indexes provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program - Classified and Unclassified Versions, Engineering Index, Nuclear Science Abstracts, TISE, List of Bibliographies in the Atomic Energy Program.

This bibliography contains 94 references on metal hydrides, with particular emphasis placed on the hydrides of titanium, yttrium, and zirconium. The bibliography covers the period 1955 through 1959. The references are arranged alphabetically by title. Sources used in compiling this bibliography are: Applied Science and Technology Index, Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program, Classified and Unclassified Parts, Industrial Arts Index, Internal Card Catalog, Monthly List of Bibliographies in the Atomic Energy Program, U.S.A.E.C. Technical Information Service Extension, Nuclear Science Abstracts.

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.

This bibliography contains 145 references on radiation effects on aluminum, elastomers, and lubricants. Also included are references on radiation units and conversion factors. The bibliography is limited to the period 1950 through 1959, with the references arranged alphabetically by title in five categories. An author index is provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Bibliographies of Interest to the Atomic Energy Program: Classified and Unclassified Versions, Monthly List of Bibliographies in the Atomic Energy Program. U.S.A.E.C. Technical Information Service Extension, Nuclear Science Abstracts.

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

This partially annotated bibliography contains references on advanced space propulsion units. References are also included on auxiliary power units, energy requirements, and mission requirements. The references are arranged alphabetically by title, with corporate author and subject indexes provided. This bibliography is issued in two parts: CNLM-2370-3, Part I, contains unclassified references; CNLM2370-3, Part II, contains classified material. Sources used in compiling this bibliography are: Abstracts of Classified Reports 1957-June 1960, Applied Science and Technology Index 1958-June 1960, ASTIA 1958-June 1960, Engineering Index 1957-1959, Industrial Arts Index 1957, Nuclear Science Abstracts 1957-June 1960, U.S. Government Publications Monthly Catalog 1958-June 1960.

This bibliography contains 20 references on the use of ultrasonic in electrodeposition and electroplating. The bibliography is limited to the period 1955 to 1959, with the references arranged alphabetically by title. Sources used in compiling this bibliography were: Applied Science and Technology Index, ASM Review of Metal Literature, Chemical Abstracts, Industrial Arts, Index, Nuclear Science Abstracts.

This partially annotated bibliography contains 334 references from papers published from 1945 to 1959 and includes references on the consumable - and nonconsumable - electrode vacuum arc melting process. References are also given on electrode preparation, furnace construction and operation, melting, sintering, vacuum techniques, and theory.

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.

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.

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.

The diffusion coefficient was calculated for the diffusion of Xe through Nb and found to be 0.064 exp (-18,600/RT).

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.

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 …

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.

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

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.

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.

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)

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 …

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.