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Waste Treatment and Disposal Problems of the Future Nuclear Power Industry

Description: The elements of waste treatment and disposal are assessed which are expected to become important in the development of the nuclear power industry of the future. Growth of the nuclear power economy is considered along with composition and quantities of anticipated waste. In addition the economic implications of waste disposal are considered. It is concluded that research should be concentrated on decontaminating off gases and on conversion of wastes to a more suitable form than liquid for storag… more
Date: January 28, 1959
Creator: Bruce, Francis Robert, 1919-
Partner: UNT Libraries Government Documents Department
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Reduction of Radioactive Waste to Solids for Ultimate Storage

Description: A procedure is presented for processing high level radioactive wastes. The steps are: pot calcination of acid and neutral waste followed by separation by distillation of the fission products from effluent liquid and gaseous streams. The fission products would be recycled to the calcination pot. After calcination, the pot contents would be stored in a controlled area for cooling and accountability.
Date: January 28, 1959
Creator: Hancher, C. W.
Partner: UNT Libraries Government Documents Department
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A Simple Calibration and Checking Facility for Fast and Slow Neutron Detectors

Description: From introduction: The principal work described below is the development and tests of a slow neutron flux generator based on a generator developed at the University of California (UCRL 8359, W. Patterson, Roger Wallace, "A Method of Calibrating Slow Neutron Detectors"). It is shown that a tolerance flux density of slow neutrons results within a cubical cavity 15 inches on an edge with 4-inch-thick walls of water or paraffin wax when a plutonium-beryllium source emitting about 7 million neutrons… more
Date: January 28, 1959
Creator: Redmond, A. H.
Partner: UNT Libraries Government Documents Department
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Toy Top Plasma Injector

Description: Introduction: "It is the purpose of this note to describe the construction and operation of the plasma injectors used in the magnetic high compression experiments in progress at the Lawrence Radiation Laboratory at Livermore. As the investigations of these injections is still in progress, remarks concerning their operation or the characteristics of the injected plasma are of a tentative nature."
Date: May 28, 1959
Creator: Coensgen, F. H.; Cummins, W. & Sherman, A.
Partner: UNT Libraries Government Documents Department
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Calculation of Effective Resonance Integrals

Description: Effective resonance integrals for fuel and fertile materials were calculated as a function of materials concentration in homogeneous media. For the fissile materials (U-235, Pu-239), results were obtained from multigroup, monte-carlo, and statistical model calculations. For the fertile materials (U-238), results were obtained from monte-carlo and multigroup calculations and were compared with experimental results.
Date: August 28, 1959
Creator: Jaye, S.
Partner: UNT Libraries Government Documents Department
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Radioactive Waste Treatment and Disposal -- a Bibliography of Unclassified Literature, Part 3

Description: This bibliography of the unclassified literature on radioactive waste treatment and disposal has been compiled from references published in the Nuclear Science Abstracts, volume 12, no. 13 (July 15, 1958) through volume 13, no. 14 (July 31, 1959). This bibliography brings up-to-date previous bibliographies published as CF-57-8-118 and CF-58-7-77.
Date: September 28, 1959
Creator: Blomeke, J. O.
Partner: UNT Libraries Government Documents Department
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Increased production from deliberate discharge cycling

Description: Considerable production gains might be attained if each reactor discharged its entire flattened region during one scheduled outage instead of utilizing several outages for this purpose. Several of the older reactors are now discharging a high percentage of their flattened zones in a single outage and could be put into this type of operation with relatively little difficulty. Production gains may be possible through better flattening efficiency, a more favorable rupture rate effect, fewer non-eq… more
Date: May 28, 1959
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Analysis of 100-K emergency water requirements after CGI-844 pump failure

Description: The demand plot has a 5-set, modified pump decay curve; it shows that 20,000 gpm emergency flow would be required within 80 seconds of complete pump power failure. Bases for the demand curve are constant bulk inlet temperature of 2 C, constant bulk outlet temperature of 95 C, K-3 I&E fuel elements, and initial reactor flow of 188,000 gpm.
Date: May 28, 1959
Creator: Corlett, R. F.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-280-A-FP: Irradiation of alloyed dingot uranium fuel elements

Description: Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 ton… more
Date: August 28, 1959
Creator: Hall, R. E. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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CGI-844: 100-K coolant back-up system scope requirements

Description: Several decisions regarding basic project philosophy must be made in order to proceed with scope design and the preparation of equipment procurement specifcations. The purpose of this document is to present as much pertinent data as possible to allow the project representatives to become familiar with the problems involved. A meeting of Representatives is planned for the near future after receipt of project authorization to discuss the scope of this project and its relationship to CG-775. Emerg… more
Date: July 28, 1959
Creator: Watson, D. F.
Partner: UNT Libraries Government Documents Department
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Neutron Age in Graphite-Water Lattices.

Description: The Fermi age of thermal neutrons in a lattice containing both water and graphite in some sort of weighted average of the age in water and in graphite independently, with correction for volumes of non-moderating elements or voids. The correct weighting function has been in question during design calculations for the NPR. This paper presents a very simple and direct approach to the problem, resulting in a weighting equation which seems to be theoretically sound. Unfortunately, simple theories ca… more
Date: October 28, 1959
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Partner: UNT Libraries Government Documents Department
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A Radiofrequency Separator For High-Energy Particles

Description: This report is an outgrowth of the MURA Users' Conference of June 1959. At that conference the group on beam separators discussed the problem of whether particle separation could be achieved at the machine energies under consideration. A preliminary version of the scheme outlined here was given at the conference. Later, after flaws were discovered, it was modified. The attempt is not to show that this is the way it should be done, but to show with reasonable certainty that there is at least one… more
Date: October 28, 1959
Creator: Good, Myron L.
Partner: UNT Libraries Government Documents Department
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PROBLEMS IN ACCOUNTABILITY MEASUREMENTS ASSOCIATED WITH THE INTERIM CHEMICAL PROCESSING PROGRAM

Description: Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarized. Experienee in comparisons of reactor (production and research) calculations vs. chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions ( plus or minus 0.54 to plus or minus 0.78%) in chemical plant measurements (bulk and analytical) for fissionable material accountab… more
Date: May 28, 1959
Creator: Arnold, E D & Gresky, A T
Partner: UNT Libraries Government Documents Department
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Volatility: Fluorinator Design FV-100, Zr-U Fuel Element Processing Phase

Description: Volatility Pilot Plant Mark III Fluorinator is a doublechamber type vessel, each chamber 2 1/2 ft by 16 in. outside diameter separated by a 5-in. pipe 15 in. long. ASME flanged and dished heads are used for the chamber tops and conical sections with a 60 deg apex angle for the chamber bottoms. A new furnace designed to maintain the complete lower chamber (molten salt+ freeboard) above melt temperature is to eliminate past experiences of salt solidification on the wall, heads, and in or on the i… more
Date: May 28, 1959
Creator: Ruch, J. B.
Partner: UNT Libraries Government Documents Department
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DEFUELING THE S2G REACTOR

Description: The defueling of the S2G Reactor which was conducted at the Electric Boat Division, General Dynamics Corporation Groton Connecticut during January 1959, is reported from the viewpoint of the participating personnel from Knolls Atomic Power Laboratory. The sequence of events is outlined, difficulties encountered during the operation are described, and conclusions of possible interest to other naval nuclear reactors are given (auth)
Date: May 28, 1959
Creator: Moore, C.V.
Partner: UNT Libraries Government Documents Department
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THE HGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH- TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO$sub 2$ FUEL ELEMENTS

Description: The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO/sub 2/ fuel appear to be less than 0.2% of thos… more
Date: July 28, 1959
Creator: Cottrell, W. B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Partner: UNT Libraries Government Documents Department
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Properties of Uranium Dioxide-Stainless Steel Dispersion Fuel Plates

Description: The physical and mechanical properties of GCRE-type fuel elements were determined from room temperature to 1650 deg F. The fuel elements were prepared by cladding Type 318 stainless steel sheet to a core containing 15 to 35 wt.% UO/ sub 2/ in either prealloyed Type 318 stainless steel or elemental iron-18 wt.% chromium-14 wt. % nickel-2.5 wt. % molybdenum. The tensile strength in the direction perpendicular to the rolling plane decreased from 24,600 psi at room temperature to 9,200 psi at 1650 … more
Date: April 28, 1959
Creator: Paprocki, S. J.; Keller, D. L. & Fackelmann, J. M.
Partner: UNT Libraries Government Documents Department
open access

Waste Treatment and Disposal Problems of the Future Nuclear Power Industry

Description: The elements of waste treatment and disposal are assessed which are expected to become important in the development of the nuclear power industry of the future. Growth of the nuclear power economy is considered along with composition and quantities of anticipated waste. In addition, the economic implications of waste disposal are considered. It is concluded that research should be concentrated on decontaminating off-gases and on conversion of wastes to a more suitable form than liquid for stora… more
Date: January 28, 1959
Creator: Bruce, F.R.
Partner: UNT Libraries Government Documents Department
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