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Removal of Radioiodine From Air Streams by Activated Charcoal

Description: Contamination of the atmosphere by radioactive isotopes of iodine constitutes a serious biological hazard and, for this reason, provisions should be made at reactors to prevent such releases in the event of an accident. The efficiency of activated charcoal for adsorption of iodine vapor from air streams was measured by using a radioactive tracer method, and efficiencies of 99.6 to 99.999+% were obtained for various conditions. Comparative tests were run with silver-plated copper ribbon. A crite… more
Date: April 1, 1960
Creator: Adams, R. E. & Browning, W. E., Jr.
Partner: UNT Libraries Government Documents Department
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A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination

Description: Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Pap… more
Date: April 28, 1960
Creator: Allemann, Rudolph Theodore
Partner: UNT Libraries Government Documents Department
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PREPARATION AND FABRICATION OF PLUTONIUM FUEL ALLOY FOR LOS ALAMOS MOLTEN PLUTONIUM REACTOR EXPERIMENT NO. 1

Description: Tantalum-sheathed plutonium fuel pins were prepared for the first core loading of the Los Alamos Molten Plutonium Reactor Experiment-I. Plutonium--10 at.% iron alloy was prepared by co-reduction and by co-melting methods. After casting the alloy into rods, each rod was machined and finished to a 0.357-in.- diameter piece weighing 175 g. The finished alloy rod was finally placed in a tantalum sheath, then sealed by fusion welding to a tantalum cap. Procedures and equipment used for alloying, cas… more
Date: April 15, 1960
Creator: Anderson, J.W.; McNeese, W.D. & Leary, J.A.
Partner: UNT Libraries Government Documents Department
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SN5001--an IBM-650 Code for Steady-State Thermal Evaluation of an Instrumented Multi-Fuel-Plate Subassembly

Description: An IBM-650 computer program, SN5001, for the calculation of steady-state thermal conditions in the fuel plates and coolant of an instrumented multi-fuel- plate subassembly is described. The program is applicable for subcooled or bulk boiling coolant conditions and surface conditions of heating, local boiling, and film boilimg, and can be used for data reduction or design. The derivation and a list of the heat conduction and coolant enthalpy equations and a description of the code sufficient for… more
Date: April 1960
Creator: Arbtin, E. & Westphal, R. B.
Partner: UNT Libraries Government Documents Department
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Evaluation of Aluminum for use in Reactors Cooled by High-Temperature Recirculating Water

Description: aluminum has been considered as a material for cladding fuel elements to be used in reactors cooled by high-temperature recirculating water. Aluminum is abundant, chap, has a relatively low cross section for thermal neutrons, and is readily fabricated into complex shapes. For these reasons, it appears that the use of aluminum rather than steel, Zircaloy or other candidate materials for fuel element cladding, would result in considerable savings in operating expense. The actual economics will of… more
Date: April 5, 1960
Creator: Ayres, J. A.
Partner: UNT Libraries Government Documents Department
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The Trumpeter Swan: its History, Habits, and Population in the United States

Description: Summary of the trumpeter swan, including geographic distribution, habitats for breeding and wintering, life cycle, nesting, food, limiting factors, longevity, population dynamics, and human management.
Date: April 30, 1960
Creator: Banko, Winston E.
Partner: UNT Libraries Government Documents Department
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Thermal Hydraulic Bases for Selected PRTR Process Specifications

Description: This document presents the bases for those PRTR Process Specifications involving considerations of heat transfer and fluid flow. It will be noted that some of the bases incorporate information gained from laboratory experiments with electrically heated test sections simulating PRTR fuel elements. These experiments are described in some detail elsewhere.
Date: April 1, 1960
Creator: Batch, J. M. & Ambrose, T. W.
Partner: UNT Libraries Government Documents Department
open access

REACTIONS OF HYDROGEN PEROXIDE AND ION EXCHANGE RESINS

Description: The interaction of dilute aqueous A/sub 2/O/sub 2/ and ion exchange resins was investigated. A mechanism of absorption and decomposition of H/sub 2/ O/sub 2/ on anion exchange resin is proposed. (auth)
Date: April 1, 1960
Creator: Baumann, E. W.
Partner: UNT Libraries Government Documents Department
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HEAT-TRANSFER EXPERIMENTS ON A PROPOSED FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION II FO FUEL-ASSEMBLY HEAT-TRANSFER AND CHANNEL PRESSURE-DROP EXPERIMENT FOR THE EGCR RESEARCH AND DEVELOPMENT PROGRAM

Description: Heat-transfer data are presented for the Experimental Gas Cooled Reactor Title I seven-rod fuel-assembly design. The effect on heat transfer of (1) the radial location of the outer six rods of the seven-fuel-rod cluster and of (2) the addition of helical-finned spacers at the midpoint of each of the seven fuel rods is discussed. The heattransfer data were obtained to verify preliminary general assumptions pertaining to the heat-transfer characteristics of the seven- rod fuel-assembly design and… more
Date: April 12, 1960
Creator: Beaudoin, C.L. & Higgins, R.M.
Partner: UNT Libraries Government Documents Department
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THE DIFFUSION OF RADIOACTIVE FISSION PRODUCTS FROM POROUS FUEL ELEMENTS

Description: The release of fission products from porous fuel elements during irradiation may be largely a diffusion process. An equivalent-sphere hypothesis was proposed to provide a model by which the diffusion can be analyzed. The equations of diffusion were previously solved for in- pile conditions. The slow convergence of the formulas makes the previous solutions awkward. In the present investigation alternate formulas were derived which are more suitable under certain circumstances. Tables were prepar… more
Date: April 18, 1960
Creator: Beck, S.D.
Partner: UNT Libraries Government Documents Department
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The Sodium Graphite Reactor: Tommorrow's Power Plant

Description: A description is given of the Advanced Sodium Graphite Reactor Power Plant, including the reactor, heat transfer systems, generatirg plant, control systems, and the economics of producing 256 Mw(e). The safety of this design is due to its unusually low operating pressure, absence of chemically incompatible materials in the core, and excellent stability under atatic and dynamic conditions. The reactor is being constructed at Hallam, Nebraska, at a probable cost of 0 to 0/kw, exclusive of the fir… more
Date: April 25, 1960
Creator: Beeley, R. J.; Lowell, E. G.; Polak, H. & Renard, J.
Partner: UNT Libraries Government Documents Department
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Plutonium Plexiglas Assemblies. Part 2

Description: Neutron multiplication measurements were made on tamped and untamped cylindrical assemblies. The assemblies consisted of plutonium metal sheet mcderated with Plexiglas. Experiments were performed to evaluate the effects of inhomogeneity. This work is a continuation of RFP-178. (auth)
Date: April 1, 1960
Creator: Bidinger, G. H.; Schuske, C. L. & Smith, D. F.
Partner: UNT Libraries Government Documents Department
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Transportability Studies : ML-1 Nuclear Power Plant

Description: Report that discusses programs to determine the transportability of the ML-1 nuclear power plant via railroad, tractor-trailer, and aircraft.
Date: April 1960
Creator: Blakley, J. W.; Alcorn, J. S.; Del Valle, L. G.; Healy, P. W.; Moran, D. H. & Scott, W. S.
Partner: UNT Libraries Government Documents Department
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Monthly Progress Report For Chemical Development Section B - January, 1960

Description: Progress is reported on dissolution of nuclear fuels, processing of irradiated fuels, solvent extraction studies, corrosion studies, ion exchange and waste treatment.
Date: April 11, 1960
Creator: Blanco, R. E. (Raymond Eugene), 1918-1987
Partner: UNT Libraries Government Documents Department
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Basis for design scope: Plutonium Reclamation Facility, Z Plant, Project CAC-880

Description: This report discuss the design of the Plutonium Reclamation Facility the capacity of which will be 300 kilograms per month or 3600 kilograms per year or plutonium. The subject facility, as the name implies, must be extremely flexible in its ability to handle a wide variety of feed materials. The new facility will be operating on a three-shift day, five-day week, 40-week year with an overall efficiency of 75 percent; twelve weeks per year will be required for ``turnaround`` time to enable campai… more
Date: April 27, 1960
Creator: Braden, D. E.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

Description: From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
Partner: UNT Libraries Government Documents Department
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Water plant modifications for increased production at B, C, D, DR, F, and H Reactors

Description: The purpose of this report is to define the extent of modifications necessary to increase capacities of the 100-B, C, D, DR, F, and H water plants for reactor flows of 90,000 95,000 105,000 and 115,000 GPM, and to provide supporting data for budget studies for increased production.
Date: April 15, 1960
Creator: Brinkman, L. B. & Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Judgment analysis of comparative C-64-F and X-8001-F alloy canned fuel element performance

Description: Fuel element component procurement requires a considerable lead time (three to four months after design is completed). Collection of data and statistical analyses to evaluate the performance of these components takes even longer. There is often reluctance to disturb the status quo in these matters without engineering recommendations; these are usually not given until the parameters are defined quantitatively with a high statistical level of significance. The purpose of this analysis is to take … more
Date: April 19, 1960
Creator: Brown, R. W.
Partner: UNT Libraries Government Documents Department
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