UNT Libraries Government Documents Department - 2,261 Matching Results

Search Results

prev Results: 217 - 240 next
open access

Project AN0115A Annual Report, 1976: Migration of Plutonium and Americium in the Lithosphere

Description: Annual report of Argonne National Laboratory project ANO115A. Abstract: Studies have been carried out on the migration of plutonium and americium in solutions flowing through porous and crushed rock and through fissures. The migration process can be described in terms of the surface absorption of these elements. In addition, chemical effects on the absorption have been observed. One of these effects is possibly due to the presence of a plutonium polymer that migrates at a more rapid rate than … more
Date: 1976
Creator: Hines, J. J.; Friedman, M. A.; Fried, S.; Atcher, Robert Whitehill; Quarterman, L. A. & Volesky, A.
Item Type: Refine your search to only Report
open access

Postirradiation Examinations of Element G-3 from the GCFR F-1 Series of Mixed-Oxide Elements After Approximately 3 at.% Burnup

Description: Post-irradiation examinations were performed on element G-3, from the GCFR F-1 series of mixed-oxide elements, after 2.6 at. % burnup in EBR-II. The 20% cold-worked Type 316 stainless steel clad G-3 element was irradiated as an encapsulated element using a stainless steel thermal barrier to achieve peak cladding temperatures of 690 degrees C at a peak power of 14.4 kW/ft. The maximum diametral increase of the element was 0.2% ..delta..D/D₀. The volatile fission products were found just above th… more
Date: February 1977
Creator: Strain, R. V.
Item Type: Refine your search to only Report
open access

Postirradiation Examinations of Fuel Pins from the GCFR F-1 Series of Mixed-Oxide Fuel Pins at 5. 5 at. % Burnup

Description: Postirradiation examinations were performed on five fuel pins from the Gas-Cooled Fast-Breeder Reactor F-1 experiment irradiated in EBR-II to a peak burnup of approximately 5.5 at. %. These encapsulated fuel pins were irradiated at peak-power linear ratings from approximately 13 to 15 kW/ft and peak cladding inside diameter temperatures from approximately 625 to 760°C. The maximum diametral change that occurred during irradiation was 0.2% .delta.D/D₀. The maximum fuel-cladding chemical interact… more
Date: May 1978
Creator: Johnson, C. E. & Strain, R. V.
Item Type: Refine your search to only Report
open access

Final Report on Test L4, a Loss-of-Flow Experiment

Description: The behavior of FTR-type, mixed-oxide, pre-irradiated "high-power-structure" fuel during a simulation of an FTR loss-of-flow accident was studied in the Mark-IIA integral TREAT loop. Analysis of the data leads to a postulated scenario (sequence and timing) of events in this test. This scenario is presented, together with the calculated timing of events obtained by use of SAS code.
Date: December 1976
Creator: Eberhart, James G.; Lo, R. & Barts, E. W.
Item Type: Refine your search to only Report
open access

Gasification of Chars Produced Under Simulated in situ Processing Conditions

Description: This effort is being directed toward support studies for the national endeavor on in situ coal gasification. This task involves the investigation of reaction-controlling variables and product distributions for the gasification of both coals and chars utilizing steam and oxygen. Included in this task is the investigation of the effects of using brackish water as the water supply. The high-pressure char gasification system has been received from the manufacturer and is currently undergoing testin… more
Date: December 1976
Creator: Fischer, J.; Lo, R.; Young, J. & Jonke, A. A.
Item Type: Refine your search to only Report
open access

Survey of Considerations Involved in Introducing CANDU Reactors into the United States

Description: The important issues that must be considered in a decision to utilize CANDU reactors in the U.S. are identified in this report. Economic considerations, including both power costs and fuel utilization, are discussed for the near and longer term. Safety and licensing considerations are reviewed for CANDU-PHW reactors in general. The important issues, now and in the future, associated with power generation costs are the capital costs of CANDUs and the factors that impact capital cost comparisons.… more
Date: January 1977
Creator: Till, C. E.; Bohn, E. M.; Chang, Y. I. & Van Erp, J. B.
Item Type: Refine your search to only Report
open access

Tritium Processing and Containment Technology for Fusion Reactors, Annual Report: July 1975-June 1976

Description: The hydrogen permeabilities of selected metals, alloys, and multiplex preparations that are of interest to fusion reactor technology are being characterized. A high-vacuum hydrogen-permeation apparatus has been constructed for this purpose. A program of studies has been initiated to develop design details for the tritium-handling systems of near-term fusion reactors. This program has resulted in a better definition of reactor-fuel-cycle and enrichment requirements and has helped to identify maj… more
Date: 1976?
Creator: Maroni, V. A.; Calaway, W. F.; Misra, B.; Van Deventer, E. H.; Wegton, J. R.; Yonco, R. M. et al.
Item Type: Refine your search to only Report
open access

Comparisons of Finite-Element Code Calculations to Hydrostatically Loaded Subassembly-Duct Experiments

Description: The Liquid Metal Fast Breeder Reactor (LMFBR) core structure consists of a matrix of hexagonal subassembly ducts. Evaluation of the safety aspects of the core structure requires that reliable computational procedures be available to predict the deformation response of the subassembly configuration to postulated local energy releases. Finite-element computer codes have been developed to calculate deflections and strains of a hexcan subassembly wrapper subjected to internal and external dynamic p… more
Date: January 1977
Creator: Ash, J. E. & Marciniak, T. J.
Item Type: Refine your search to only Report
open access

Generalized Parametric Model for Transient Gas Release and Swelling in Oxide Fuels

Description: The need for a capability to predict transient fission gas behavior arises because of the complexity of fission gas response to transient conditions, the importance of fission gas to fuel mechanical response, and the prevalent limitations on experimental information relevant to the problem. A detailed mechanistic analysis of intra-granular swelling and release of gas from grains to grain boundaries, both as they result from transient heating, has been developed and incorporated in a fission gas… more
Date: January 1977
Creator: Gruber, E. E.
Item Type: Refine your search to only Report
open access

Theoretical Studies of the Atmospheric Triatomic Molecules H₂O, N₂O, NO₂, CO₂, O₃, and their Ions

Description: Definitive location of excited energy levels and the delineation of reaction mechanisms were provided by ab initio calculations of the triatomic atmospheric molecules and their ions. Linear geometry to bent geometry correlation diagrams were also determined. These provide simple ways of predicting reaction possibilities. Potential energy surfaces were computed for the ground ²B₁ and ²B₂ states of H2O⁺. Previous theoretical spectra of carbon dioxide were shown to be of limited accuracy and there… more
Date: 1977?
Creator: Wahl, Arnold C.; England, Walter B.; Rosenberg, Bruce J.; Hopper, Darrel G. & Fortune, Patrick J.
Item Type: Refine your search to only Report
open access

Occurrence of Critical Heat Flux During Blowdown with Flow Reversal

Description: A small-scale experiment using Freon-11 at 130 degrees F (54.4 degrees C) and 65 psia (0.45 MPa) in a well-instrumented, transparent annular test section was used to study the occurrence of critical heat flux (CHF) during blow-down with flow reversal. The inner stainless steel tube of the annulus was uniformly heated over its 61-cm length. Inlet and exit void fractions were measured by a capacitance technique. Flow-regime transition was observed with high-speed photography. A 1-hr contact time… more
Date: January 1977
Creator: Leung, J. C. M.
Item Type: Refine your search to only Report
open access

Materials Science Division Coal Technology Quarterly Report: October-December 1976

Description: Quarterly report of the Argonne National Laboratory Materials Science Division regarding coal technology research and development. This report discusses a project for the economical conversion of coal into cleaner and more usable fuels: evaluation of ceramic-refractories exposed to abrasion-corrosion caused by coal slag, evaluation of ceramic coatings and refractories exposed to erosive environments, development of nondestructive evaluation methods applicable to coal-conversion systems, develo… more
Date: 1977?
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
open access

Coal Liquefaction Support Studies

Description: A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate th… more
Date: 1977?
Creator: Fischer, J.; Bump, T. R.; Mulcahey, T. P.; Jonke, A. A.; Lo, R.; Nandi, S. et al.
Item Type: Refine your search to only Report
open access

Laboratory Support for in situ Gasification Reaction Kinetics. Quarterly Report, October-December 1976

Description: This work, which is part of the ANL energy program for ERDA, is directed toward studies for the national endeavor on in situ coal gasification. The objective of this work is to determine the reaction-controlling variables and reaction kinetics for gasification of chars resulting when coal is pyrolyzed in underground gasification. The reactions to be studied include steam-char, carbon dioxide-char, hydrogen-char, and water gas shift reaction. Discussed in this report are the effects on the reac… more
Date: January 1977
Creator: Fischer, J.
Item Type: Refine your search to only Report
open access

Cracking and Healing Behavior of UO2 as Related to Pellet-Cladding Mechanical Interaction : Interim Report, July 1976

Description: A direct-electrical-heating apparatus has been designed and fabricated to investigate those nuclear-fuel-related phenomena involved in the gap closure-bridging annulus formation mechanism that can be reproduced in an out-of-reactor environment. Prototypic light-water-reactor uranium dioxide fuel-pellet temperature profiles have been generated utilizing high flow rates (approximately 700 liters/min) of helium coolant gas, and a re-circulating system has been fabricated to permit tests of up to 1… more
Date: October 1976
Creator: Kennedy, C. R.; Yaggee, F. L.; Voglewede, J. C.; Kupperman, D. S.; Wrona, B. J.; Ellingson, W. A. et al.
Item Type: Refine your search to only Report
open access

Bibliography for Transportation Energy Conservation

Description: A listing is given of 578 reports, books, articles, and conference papers on transportation and energy. Coverage is primarily on U. S. developments and research from 1970 to 1975. Following a section of citations of general works on energy, the bibliography contains two main parts: ''Energy for Transportation'' and ''Transportation of Energy.'' Within each of these topics the arrangement is multimodal (at the urban, regional, national, or international level), then by mode. Selected information… more
Date: May 1976
Creator: Northwestern University (Evanston, Ill.). Transportation Center. Library.
Item Type: Refine your search to only Report
open access

Feasibility of Underground Storage/Disposal of Noble Gas Fission Products

Description: The quantities of krypton-85 that can be released to the environment from nuclear energy production are to be limited after 1983 by Federal regulations. Although procedures for collecting the krypton-85 released in the nuclear fuel cycle have been developed to the point that they are commercially available, procedures for terminal disposal of the collected gas are still being examined for their feasibility. In this work, the possibilities of underground disposal of krypton-85 by several techniq… more
Date: August 1979
Creator: Winar, R. M.; Trevorrow, L. E. & Steindler, M. J.
Item Type: Refine your search to only Report
open access

Reactor Physics Studies in the Steam Flooded GCFR-Phase 2 Critical Assembly

Description: A possible accident scenario in a Gas-Cooled Fast Reactor (GCFR) is the leakage of secondary steam into the core. Considerable analytical effort has gone into the study of the effects of such an accidental steam entry. The work described in this report represents the first full scale experimental study of the steam-entry phenomenon in GCFRs. The reference GCFR model used for the study was the benchmark GCFR Phase II assembly, and polyethylene foam was used to provide a very homogeneous steam si… more
Date: August 1978
Creator: Bhattacharyya, S. K.
Item Type: Refine your search to only Report
open access

An Ultrasonic Scanner for Stainless Steel Weld Inspections

Description: The large grain size and anisotropic nature of stainless steel weld metal make conventional ultrasonic testing very difficult. This paper evaluates a technique for minimizing the coherent noise in stainless steel weld metal. The method involves digitizing conventional A-scan traces and averaging them with a minicomputer. Results are presented for an ultrasonic scanner which interrogates a small volume of the weld metal while averaging the coherent ultrasonic noise.
Date: September 1978
Creator: Kupperman, D. S. & Reimann, K. J.
Item Type: Refine your search to only Report
open access

Second Mechanized In-Service Inspection of EBR-2 Steam Generator

Description: The second mechanized ultrasonic inspection of evaporation EV-702, part of the EBR-II steam-generator system, was completed in March 1978. The 2 1/2 Cr-1 Mo duplex tubes were inspected from the bore (water) side for flaws and changes in wall thickness and for evaluating the condition of the braze between the tubes. An addition to this second inspection was the use of an ultrasonic probe to search for circumferential flaws. The inspection equipment was thoroughly checked and routinely calibrated… more
Date: November 1978
Creator: Longua, K. J.; Whitham, G. K.; Allen, C. C. & Larson, H. A.
Item Type: Refine your search to only Report
open access

Disposal of Radioactive Sodium Waste

Description: Operation of liquid-metal-cooled fast breeder reactors (LMFBRs) will result in production of various quantities of radioactive sodium waste. Two methods have been developed and tested on a small scale for converting this sodium waste to inert compounds suitable for disposal. The first method is direct oxidation of the sodium after dispersal in a silica matrix. The sodium is mixed with silica and oxidized in a rotary drum reactor. The product is suitable for making glass when other stabilizing c… more
Date: September 1978
Creator: McPheeters, C. C. & Wolson, R. D.
Item Type: Refine your search to only Report
open access

IPNS: a National Facility for Condensed Matter Research

Description: This report has been prepared to present a summary description of the Intense Pulsed Neutron System (IPNS). The principal purpose of the document is to assemble the relevant information in a concise and integrated format so that the scientific community and others interested can obtain an accurate impression of the IPNS facilities and their intended purpose. The background and technology for pulsed neutron sources are summarized.
Date: November 1978
Creator: Carpenter, J. M.; Price, D. L. & Swanson, N. J.
Item Type: Refine your search to only Report
Back to Top of Screen