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in subjects: "Actinide Compounds"

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Tumor production in Syrian hamsters following inhalation of PuO/sub 2/--ZrO/sub 2/ aerosol

Syrian golden hamsters of both sexes were exposed to aerosols of ZrO/sub 2/ containing PuO/sub 2/. The starting material in the aerosol generator also had a small amount of /sup 57/Co added as a tracer. The mixture of all three constituents was nebulized and the droplets passed through a heating column at 1000/sup 0/C. Aerosol sampling was accomplished with a cascade impactor and electrostatic precipitator. The median aerodynamic diameters in all inhalation runs were approximately 2 ..mu..m wit… more

Date: January 1, 1978

Creator: Thomas, R. G. & Smith, D. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Redox reactions involving chromium, plutonium, and manganese in soils

Plutonium speciation in soils is discussed. Chromium was selected as a model for studying soil Pu. Similarities between Cr and Pu are pointed out, and a hypotheses concerning Pu speciation in soils is presented. Findings from Cr oxidation studies that may be relevant to the problem of Pu oxidation in soils are discussed. (JGB)

Date: January 1, 1979

Creator: Amacher, M.C. & Baker, D.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

TCT hybrid preconceptual blanket design studies

The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal d… more

Date: January 1, 1978

Creator: Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Interaction of noble-metal fission products with pyrolytic silicon carbide

Fuel particles for the High-Temperature Gas-Cooled Reactor (HTGR) contain layers of pyrolytic carbon and silicon carbide, which act as a miniature pressure vessel and form the primary fission product barrier. Of the many fission products formed during irradiation, the noble metals are of particular interest because they interact significantly with the SiC layer and their concentrations are somewhat higher in the low-enriched uranium fuels currently under consideration. To study fission product-… more

Date: January 1, 1982

Creator: Lauf, R. J. & Braski, D. N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Preliminary study of the favorability for uranium in the Madera Limestone, and Cutler and Chinle Formations of the Sierra Nacimiento-Jemez Mountains area, New Mexico

Small, surficial, secondary uranium deposits are present in several formations in the Sierra Nacimiento-Jemez Mountains region, but none of significant size are known. Field surveys indicate that the deposits are laterally discontinuous and are, in most cases, associated with carbonaceous debris. Mineral contents of as much as 0.18 percent U/sub 3/O/sub 8/ are recorded. There are 2 known deposits in the Pennsylvanian Madera Limestone, 18 in the Permian Cutler Formation, and 3 in the Triassic Ch… more

Date: January 1, 1978

Creator: Vizcaino, H. P.; O'Neill, A. J. & Dotterer, F. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Magnetic measurements of the transuranium elements. Progress report, January 1-December 31, 1986

Magnetic measurements have been made on polycrystalline CfCl/sub 3/ in both a hexagonal and orthorhombic crystal form. The magnetic properties were studied as a function of crystal structure by converting the same sample back and forth from one form to the other. In a continuation of a study of the magnetic transition temperature as a function of actinide-actinide separation of the curium pnictide series we have undertaken magnetic measurements on curium bismuthide during this contract period. … more

Date: September 1, 1986

Creator: Nave, S.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Development of an extended-burnup Mark B design. First semi-annual progress report, July-December 1978. Report BAW-1532-1. [PWR]

The primary objective of this program is to develop and demonstrate an improved PWR fuel assembly design capable of batch average burnups of 45,000-50,000 MWd/mtU. To accomplish this, a number of technical areas must be investigated to verify acceptable extended-burnup fuel performance. This report is the first semi-annual progress report for the program, and it describes work performed during the July-December 1978 time period. Efforts during this period included the definition of a preliminar… more

Date: October 1, 1979

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Plutonium isotopic analysis of highly enriched mixed oxides

We investigated the analysis method used by the International Atomic Energy Agency (IAEA) to determine the plutonium isotopic composition of highly enriched mixed oxides (MOX). The IAEA currently uses the Cicero multichannel analyzer and the IAEAPU algorithm for its analysis. In our investigation the plutonium isotopic measurements were found to be good for PuO/sub 2/ powder or low-enriched MOX, but acceptable for highly enriched MOX in IAEA special nuclear material (SNM) accountability applica… more

Date: August 1, 1986

Creator: Clement, S. D. & Augustson, R. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO/sub 2//UO/sub 2/ (95%/5%) fuel from the Elk River Reactor, irradiate… more

Date: January 1, 1980

Creator: Pickett, J.B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Investigation of breached depleted UF sub 6 cylinders

In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. An investigation team was immediately formed to determine the cause of the failures and their impact on future storage procedures and to recommend corrective actions. Subsequent investigation showed that the failures most probably resulted from mechanical damage that oc… more

Date: January 1, 1991

Creator: DeVan, J. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Pu-238 fuel form activities, February 1-28, 1985

The Plutonium Fuel Form Facility (for producing /sup 238/PuO/sub 2/ for RTG's) remains in a production readiness mode of operation. (DLC)

Date: August 1, 1985

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Some Scoping Experiments for a Space Reactor

Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failur… more

Date: July 7, 1983

Creator: Alexander, C. A. & Ogden, J. S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Analysis of the thorium axial blanket experiments in the PROTEUS reactor

An extensive program of reactor physics experiments in GCFR fuel pin lattices has been completed recently at the PROTEUS critical facility located at EIR laboratory in Switzerland. The PROTEUS reactor consists of a central test zone surrounded by a uranium buffer and thermal driver region. The test lattices included a PuO/sub 2//UO/sub 2/ fuel region with internal and axial blankets of UO/sub 2/, ThO/sub 2/, and thorium metal. Detailed analysis of the thorium-bearing lattices has been performed… more

Date: January 1, 1980

Creator: White, J.R.; Ingersoll, D.T. & Schmocker, U.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

MHD compressor---expander conversion system integrated with GCR inside a deployable reflector

This work originates from the proposal MHD Compressor-Expander Conversion System Integrated with a GCR Inside a Deployable Reflector''. The proposal concerned an innovative concept of nuclear, closed-cycle MHD converter for power generation on space-based systems in the multi-megawatt range. The basic element of this converter is the Power Conversion Unit (PCU) consisting of a gas core reactor directly coupled to an MHD expansion channel. Integrated with the PCU, a deployable reflector provides… more

Date: April 20, 1989

Creator: Tuninetti, G. (Ansaldo S.p.A., Genoa (Italy). Research Div.); Botta, E.; Criscuolo, C.; Riscossa, P. (Ansaldo S.p.A., Genoa (Italy). Nuclear Div.); Giammanco, F. (Pisa Univ. (Italy). Dipt. di Fisica) & Rosa-Clot, M. (Florence Univ. (Italy). Dipt. di Fisica)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Preparation of curium-americium oxide microspheres by resin-bead loading

Resin-bead loading and calcination techniques have been used to produce all curium and americium oxide feed material (about 2.2 kg) for HFIR targets since 1971. The process based on Dowex 50W resin has progressed from a series of test runs, through special production runs, into routine production in permanent equipment beginning in 1975. Key attributes of this process are its reliability, high yields, and ease of operation. The process is suited for remote operation in hot cells. Yields approac… more

Date: January 1, 1980

Creator: Chattin, F. R.; Benker, D. E.; Lloyd, M. H.; Orr, P. B.; Ross, R. G. & Wiggins, J. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermodynamics of the Fuel Fragmentation Gas

In the context of nuclear reactor safety studies, a program is in progress at ORNL whereby fuel-fragmentation situations are mocked up by the application of high-current capacitor discharges through solid UO/sub 2/ samples. The goal of the present work is to predict such quantities as the number of gas and liquid fragments and their energy distributions. The point of view adopted is that upon fragmentation, a cloud of UO/sub 2/ vapor is formed containing ''primeval'' liquid fragments which act … more

Date: January 1, 1977

Creator: Perez, R. B. & Alsmiller, R. G., Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Uranium hexafluoride: Safe handling, processing, and transporting: Conference proceedings

This conference seeks to provide a forum for the exchange of information and ideas of the safety aspects and technical issue related to the handling of uranium hexafluoride. By allowing operators, engineers, scientists, managers, educators, and others to meet and share experiences of mutual concern, the conference is also intended to provide the participants with a more complete knowledge of technical and operational issues. The topics for the papers in the proceedings are widely varied and inc… more

Date: January 1, 1988

Creator: Strunk, W.D. & Thornton, S.G. (eds.)

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Radiation standards and calibrations. FY-1981 annual report

The research program encompasses: reviewing calibration standards, regulations, and handbooks; assuring that calibration procedures used are in agreement with technically accepted methods; maintaining basic radioactive sources and instruments that serve as radiological standards; and providing traceability to the National Bureau of Standards where possible. In addition, major efforts are being expended to upgrade the 318 calibration facility. This report focuses on major accomplishments during … more

Date: July 1, 1982

Creator: Roberson, P. L.; Yoder, R. C.; Fox, R. A.; Hooker, C. D.; Hogan, R. T.; Holbrook, K. L. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Kilowatt isotope power system. Phase II plan. Volume V. Safety, quality assurance and reliability

The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a /sup 238/PuO/sub 2/-fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Included in this volume are: launch and flight safety considerations; quality assurance techniques and procedures to be followed through system fabrication, assembly and inspection; and the reliability program ma… more

Date: March 15, 1978

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Phonon dispersion relation of uranium nitrate above and below the Neel temperature

Neutron coherent inelastic scattering measurements have been made of the phonon dispersion relation of uranium nitride both above and below the Neel temperature T/sub N/ = 50 K. Within the precision of the measurements, about 1% in frequency and 10% in line width and in scattered neutron intensity, no significant changes in these phonon properties were observed as a function of temperature other than those arising from population factor changes and a small stiffening of the lattice as the tempe… more

Date: January 1, 1977

Creator: Dolling, G; Holden, T M; Evensson, E C; Buyers, W J.L. & Lander, G H

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Neutronics of a mixed-flow gas-core reactor

The study was made to investigate the neutronic feasibility of a mixed-flow gas-core reactor. Three reactor concepts were studied: four- and seven-cell radial reactors and a seven-cell scallop reactor. The reactors were fueled with UF/sub 6/ (either U-233 or U-235) and various parameters were varied. A four-cell reactor is not practical nor is the U-235 fueled seven-cell radial reactor; however, the 7-cell U-233 radial and scallop reactors can satisfy all design criteria. The mixed flow gas cor… more

Date: November 1, 1977

Creator: Soran, P. D. & Hansen, G. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Environmental radiation safety: source term modification by soil aerosols. Interim report

The goal of this project is to provide information useful in estimating hazards related to the use of a pure refractory oxide of /sup 238/Pu as a power source in some of the space vehicles to be launched during the next few years. Although the sources are designed and built to withstand re-entry into the earth's atmosphere, and to impact with the earth's surface without releasing any plutonium, the possibility that such an event might produce aerosols composed of soil and /sup 238/PuO/sub 2/ ca… more

Date: August 1, 1980

Creator: Moss, O.R.; Allen, M.D.; Rossignol, E.J. & Cannon, W.C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

New computer-controlled precipitator at the Savannah River Plant

A new plutonium triflouride preciptation facility was successfully started up on the first attempt May 13, 1987 at the Savannah River Plant (SRP). This new facility provided a 75% reduction in radiation exposure, a substantial improvement in process performance, and elimination of the major SRP process bottleneck. This was accomplished through sound engineering, improved process control, process automation, and extensive testing of components, assemblies, and entire system prior to ''… more

Date: January 1, 1988

Creator: Moore, E. N.; Robbins, C. C. & Murdock, D. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Arsenic Removal From Gaseous Streams

Uranium feed materials, depending on the production process, have been found to contain arsenic (As) as a contaminant. Analyses show the As to be present as As pentafluoride (AsF{sub 5}) and/or hexafluoroarsenic acid (HAsF{sub 6}) and enter the enrichment cycle through contaminated hydrogen fluoride (HF). Problems related to corrosion of cylinder valves and plugging of feed lines and valves have been attributed to the As. Techniques to separate AsF{sub 5} from uranium hexafluoride (UF{sub 6}) u… more

Date: November 22, 1989

Creator: Russell, R. G. & Otey, M. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department