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EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATION ON BURNOUT HEAT FLUX WITH BOILING WATER. Final Summary Report, October 3, 1960-July 31, 1961

Description: Experimental results were obtained on the effect of an ultrasonic field on the burnout heat flux for water flowing at atmospheric pressure, through an annular flow channel formed by a 1/4-in.-diameter electrically heated tube and a concentric glass tube of 3/4-in. ID. The active length of the central heating element was 5 1/2 in. The ultrasonic transducer, which was operated at 25,000 cps and a maximum electrical input of 300 watts, was located at the inlet end of the flow channel. The ultrason… more
Date: July 31, 1961
Creator: Romie, F.E. & Aronson, C.A.
Partner: UNT Libraries Government Documents Department
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Investigations of Radioactive Fuel-Bearing Glasses

Description: "A series of glass compositions containing uranium oxide was investigated to determine fiberizability and physical properties of resultant fibers. The basic properties to be determined were the maximum U/sub 3/O/sub 8/ content in a fiberizable glass and the maximum service temperature of the fibers. Glasses containing 60 wt% U/sub 3/O/sib 8/ were fiberizable; the fibers had strengths of 100,000 psi at 1600 deg F. Fiber-forming equipment was installed at Moun Laboratory to produce glass fibers c… more
Date: July 31, 1961
Creator: Lockwood, P. A.
Partner: UNT Libraries Government Documents Department
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The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)

Description: "An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
Date: July 30, 1961
Creator: Gehman, William G.
Partner: UNT Libraries Government Documents Department
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SM-2 Full Scale Flow Studies Termination Report

Description: Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of wate… more
Date: July 30, 1961
Creator: Christenson, J. A.; Richards, W. M. S. & Davidson, S. L.
Partner: UNT Libraries Government Documents Department
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THERMAL EXPANSION OF SNAP MATERIALS

Description: Thermal expansion characteristics were determined for fuel-moderator, reflector, cladding, and engineering erials within the SNAP-2 core vessel. Values were denined for AISI Type 347 stainless steel, Hastelloy N, Zr, ZrH, and zirconium --uranium hydrides, from room temperature to temperatures greater than 1300 deg F. Derived equations were calculated for these materials, using a least squares analysis. Thermal expansion coefficients for the temperature range of 77 to 1200 deg F are: 10.34 x 10/… more
Date: July 30, 1961
Creator: Watrous, J.D.
Partner: UNT Libraries Government Documents Department
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Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Description: Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
Partner: UNT Libraries Government Documents Department
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Test of Buried Structural-Plate Pipes Subjected to Blast Loading

Description: From abstract: Two 20-ft-long 7-ft-diameter 10-gauge structural-plate pipes, having longitudinal joints with eight bolts per foot, were buried and tested in the Smoky event of Operation Plumbbob at predicted pressure levels of 195 and 265 psi. The depth of burial was 10 ft over the crown of the pipe.
Date: July 28, 1961
Creator: Williamson, R. A. & Huff, P. H.
Partner: UNT Libraries Government Documents Department
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Applied Health Physics Annual Report for 1960

Description: Although there were the ususl fluctuations in background at certain of the monitoring stations, the contamination levels recorded do not differ significantly from those of the previous year except that there appears to be a slight trend downward. Data are tabulated. This downward trend can be attributed to a curtailment of operations at the Laboratory, the gradual implementation of the containment program, and a curtailment in world-wide weapons testing. Tall-out data are included. Two personne… more
Date: July 27, 1961
Partner: UNT Libraries Government Documents Department
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Design of supplement A to production test IP-183-A-98-FP evaluation of projection fuel elements in K process tubes

Description: Fuel element misalignment is an apparent cause of ``hot-spot`` ruptures. Several methods of eliminating hot spots have been tried, however, none appear to have completely solved the hot-spot problem. Attachment of projections to the side of the fuel elements appears to offer a means of minimizing misalignment since they act as bumpers against the side of the process tubes. Preliminary data from tests now in progress or recently completed indicate excessive corrosion rates are not to be expected… more
Date: July 27, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-409-A-FP, pilot test of self-supported fuel elements in K size smoothbore zirconium process tubes

Description: In the Plant Improvement Program, it is proposed to retube the K-Reactors with standard size Zircaloy-2 smooth-bore process tubes and to charge self supported fuel elements starting March 15, 1964. The first step in support of this transition program is to confirm compatibility of the fuel-tube geometry and secondly to obtain fuel-tube performance information prior to full scale commitment of the K-Reactors to this design. In view of the testing of self-supported fuel which has been accomplishe… more
Date: July 26, 1961
Creator: Clinton, M. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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The High Temperature Heat Contents and Related Thermodynamic Properties of Lanthanum, Praseodymium, Europium, Ytterbium, and Yttrium

Description: The high temperature enthalpies of five rare earths were measured from 0 to 1100 deg C using a Bunsen ice calorimeter. The enthalpy of yttrium metal was studied from 1100 to 1675 deg C using a modified high temperature vacuum Bunsen calorimeter. The data were fitted to empirical equations from which the heat of transition and fusion, the heat capacity, and the related thermodynamic quantities were calculated. These results confirmed indications from other properties that europium and ytterbium … more
Date: July 26, 1961
Creator: Berg, J. R.; Spedding, F. H. & Daane, A. H.
Partner: UNT Libraries Government Documents Department
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The High Temperature Heat Contents and Related Thermodynamic Properties of Lanthanum, Praseodymium, Europium, Ytterbium and Yttrium

Description: From abstract: "The high temperature enthalpies of five rare-earth metals were measured from 0° to 1100°C using a Bunsen ice calorimeter. The enthalphy of yttrium metal was studied from 1100° to 1675°C using a modified high temperature vacuum Bunsen calorimeter. The data were fitted to empirical equations from which the heat of transition and fusion, the heat capacity, and the related thermodynamic quantities were calculated. These results confirmed indications from other properties that europi… more
Date: July 26, 1961
Creator: Berg, J. R.; Spedding, F. H. (Frank Harold), 1902- & Daene, A. H.
Partner: UNT Libraries Government Documents Department
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STRUCTURE AND USE OF ALGOL 60

Description: ALGOL 60 is a universal, algebraic, machine-independent programming language. It was designed by a group representing computer societies from many different countries. Its primary aims are: (1) simplification of program preparation, (2) simplification of program exchange, and (3) incorporation of the important programming techniques presently known. An elaboration of the concepts of ALGOL 60 is given, mostly with the help of illustrative examples. (auth)
Date: July 26, 1961
Creator: Bottenbruch, H.
Partner: UNT Libraries Government Documents Department
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Barytes Concrete for Radiation Shielding: Mix Criteria and Attenuation Characteristics

Description: Concrete mix design criteria, based on existing theories of proportioning and specifically oriented toward the solution of radiation shielding problems, were developed. Effects of aggregate gradation, cement-to- aggregate ratio, and water content were examined. A barytes concrete, designed according to these criteria, was thoroughly investigated in the Lid Tank Shielding Facility. Relative effectivenesses of dry aggregates, aggregates plus cement, and cured concrete were compared through therma… more
Date: July 25, 1961
Creator: Grantham, W.J. Jr.
Partner: UNT Libraries Government Documents Department
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Experimental Measurements of the Suction Head Required by the Hallam Prototype Free Surface Sodium Pump

Description: Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)
Date: July 25, 1961
Creator: Atz, R. W.
Partner: UNT Libraries Government Documents Department
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1A HEAT EXCHANGER LEAK TEST. CORE I, SEED 2. Test Evaluation. Section 2

Description: An investigation was conducted to determine which tubes of the 1A loop heat exchanger are leaking. Air pressure and probing tests are inconclusive and cannot be used to verify chemical sampling. (J.R.D.)
Date: July 24, 1961
Partner: UNT Libraries Government Documents Department
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TrU Facility - Alpha Box Accessories - Manipulator Operable Spherical Joint Clamp

Description: A special clamp has been designed and developed which is manipulator operable and which will clamp a standard spherical (glass) joint. This version of the clamp can be pre-adjusted to securely lock on the joint, owing to the incorporation of an adjustable seat for the over-center clamp.
Date: July 22, 1961
Creator: Klima, B.B.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: June 1961

Description: This report, for June 1961 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: July 21, 1961
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2

Description: The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification… more
Date: July 21, 1961
Partner: UNT Libraries Government Documents Department
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PM-3A Nuclear Power Plant Program

Description: From summary: Progress report on the production of detailed piping and equipment installation drawings for the PM-3A nuclear power plant program. Attention has been paid to the procurement of those valves and specialty items associated with the piping system.
Date: July 21, 1961
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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