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Estimate of Hazard Produced by Accidental Release of Gaseous Fission Products from an ORR Fused Salt Capsule Experiment

Description: An accidental release of gaseous fission products from an ORR fused salt capsule, containing 26 mg. of U/sup 235/, was postulated and the resuiting hazard estimated by calculating the maximum external and internal dose an individual could receive from exposure to the gaseous fission products and their decay products. Assuming all the contained gaseous fission produets are released, the resulting external and internal dosc, to organs other than the thyroid, arc insignificant. The dose to the thy… more
Date: April 24, 1959
Creator: Adams, R. E. & Browning, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of neutronics information for irradiation experiments in the Oak Ridge Research Reactor

Description: Neutronics information is summarized for several experiments in the irradiation facilities of the Oak Ridge Research Reactor (ORR). Comparisons are made between experimental data and results obtained from calculational models. Factors that significantly influence the neutronic characteristics of the irradiation facilities are identified, and experimental neutron dosimeter materials and techniques are described.
Date: May 1, 1976
Creator: Allen, E. J. & Kerr, H. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-core nuclear heating rates easily measured with proven calorimetric instruments

Description: Calorimetric instruments have been developed for directly measuring in-core nuclear heating rates in selected materials. The calorimeters, which are small, easy to fabricate, and easy to operate, permit precise measurement of both low and high in-core nuclear heating rates. Prototype instruments were successfully tested in the Oak Ridge Research Reactor (ORR). Fission rates in /sup 235/U and gamma heating rates in aluminum were measured at eight axial positions in experimental facility E-5 and … more
Date: January 1, 1977
Creator: Allen, E. J.; Kerr, H. T. & Mincey, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Description of Ornl Pool Type Critical Facility

Description: The Pool Type Critical Facility (PTCF) is a low powered, highly eariched (90 to 95% U/sup 235/) ordinary light water cooled and moderated, beryllium oxide reflected assembly. It is generally similar to the present BSR at ORNL, the principal modification being that the grid plate is arranged to accommodate both ORR and BSR fuel elements. The PTCF is located in the northwest corner of the existing BSR pool. The 9 x 7 lattice provides 63 fuel, control rod, or reflector positions. (W.D.M.)
Date: July 16, 1957
Creator: Bates, A. E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Vapor Containment in the Oak Ridge Research Reactor

Description: Containment of the ORR is attained by means of a ventilation system which is capable of exhausting air from the building at a rate sufficient to ensure that all leakage of air at ground level is into the building. The exhaust air is treated by scrubbing and filtration and is discharged from a large stack at a height and velocity sufficient to guarantee that meteorological dispersion will reduce the resulting concentration of radioactive material to an acceptable level. Factors involved in selec… more
Date: August 23, 1962
Creator: Binford, F.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ORR Operations for Period April 1961 to April 1962

Description: A summary of the activities in the 4th operational year is presented for the ORR. On-stream time at 30 Mw was relatively steady with 75.4 and 83.7% representing the lowest and highest quarters. Modification of the ball-latch mechanism of the shim-rod-drives is in progress. The primary cooling system bypass control valve was modified and a d-c pony motor was added at the No. 3 primary pump. This addition was made to increase the reliability of adequate water flow for afterheat cooling. A study o… more
Date: October 16, 1962
Creator: Binford, F.T.; Casto, W.R. & Colomb, A.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of reactor kinetic parameters without the need for perturbation codes.

Description: The analysis of research reactor transients depends on the effective delayed neutron fraction (k{sub eff}), its family-dependent components ({beta}{sub eff,i}), the prompt neutron lifetime (l{sub p}), and the decay constants ({lambda}{sub i}) for each delayed neutron family. Beginning with ENDF/B-V data, methods are presented for accurately calculating these kinetic parameters within the framework of diffusion theory but without the need for a perturbation code. For heavy water systems these me… more
Date: January 14, 1998
Creator: Bretscher, M. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analytical support for the ORR (Oak Ridge Research Reactor) whole-core LEU U/sub 3/Si/sub 2/-Al fuel demonstration

Description: Analytical methods used to analyze neutronic data from the whole-core LEU fuel demonstration in the Oak Ridge Research Reactor are briefly discussed. Calculated eigenvalues corresponding to measured critical control rod positions are presented for each core used in the gradual transition from an all HEU to an all LEU configuration. Some calculated and measured results, including ..beta../sub eff//l/sub p/, are compared for HEU and LEU fresh fuel criticals. Finally, the perturbing influences of … more
Date: January 1, 1986
Creator: Bretscher, M.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluation of differential shim rod worth measurements in the Oak Ridge Research Reactor

Description: Reasonable agreement between calculated and measured differential shim rod worths in the Oak Ridge Research Reactor (ORR) has been achieved by taking into account the combined effects of negative reactivity contributions from changing fuel-moderator temperatures and of delayed photoneutrons. A method has been developed for extracting the asymptotic period from the shape of the initial portion of the measured time-dependent neutron flux profile following a positive reactivity insertion. In this … more
Date: January 1, 1987
Creator: Bretscher, M.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The ORR Whole-Core LEU Fuel Demonstration

Description: The ORR Whole-Core LEU Fuel Demonstration, conducted as part of the US Reduced Enrichment Research and Test Reactor Program, has been successfully completed. Using commercially-fabricated U{sub 3}Si{sub 2}-Al 20%-enriched fuel elements (4.8 g U/cc) and fuel followers (3.5 g U/cc), the 30-MW Oak Ridge Research Reactor was safely converted from an all-HEU core, through a series of HEU/LEU mixed transition cores, to an all-LEU core. There were no fuel element failures and average discharge burnups… more
Date: January 1, 1990
Creator: Bretscher, M.M. & Snelgrove, J.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fuel element powers, STVU masses, and burnups from gamma-scanning data: Preliminary analysis of irradiated ORR (Oak Ridge Research Reactor) LEU fuel elements

Description: Fuel elements used in the ORR whole-core LEU fuel demonstration have been gamma-scanned to determine axial distributions of UZLa and TXCs fission product activities. This data has been analyzed to determine cycle-averaged fuel element powers, residual STVU masses, and burnups of discharged fuel elements. Methods used to analyze the data are discussed and results are presented for the LEU fuel elements. Measured and calculates fuel element powers agree to within 5%, residual STVU masses to withi… more
Date: January 1, 1988
Creator: Bretscher, M.M.; Snelgrove, J.L. & Hobbs, R.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Interpretation of gamma-scanning data from the ORR demonstration elements

Description: The HEU and LEU fuel elements used in the ORR whole-core demonstration were gamma-scanned to determine the axial distribution of the {sup 140}La and {sup 137}Cs activities. Analysis of this data is now complete. From the {sup 140}La activity distributions cycle-averaged powers were determined while the {sup 137}Cs data provided a measure of the final {sup 235}U burnup in the fuel elements. A method for calculating correction factors for activity gradients transverse to the fuel element axis is … more
Date: January 1, 1989
Creator: Bretscher, M.M.; Snelgrove, J.L.; Hobbs, R.W. (Argonne National Lab., IL (USA) & Oak Ridge National Lab., TN (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

GENERAL STANDARDS GUIDE FOR EXPERIMENTS IN ORNL RESEARCH REACTORS

Description: The Oak Ridge National Laboratory has three generalpurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the safe safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to… more
Date: August 20, 1962
Creator: Cagle, C.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SAFETY AND OPERABILITY REVIEW OF EXPERIMENTS TO BE OPERATED IN NUCLEAR REACTORS AT ORNL

Description: The operation of the tests and experiments conducted in the ORR, the LITR, and the ORNL Graphite Reactor is discussed. In order to minimize the possibility of any hazardous conditions developing into an incident involving the safety of personnel, the reactor, and other equipment, any experiment design and installation should be checked or reviewed to ensure that all conceivable dangers are recognized and that appropriate safeguards have been incorporated into the design. (W.D.M.)
Date: December 1, 1958
Creator: Cagle, C.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Oak Ridge National Laboratory Research Reactor Experimenters' Guide

Description: The Oak Ridge National Laboratory has three multipurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the same safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to t… more
Date: October 1, 1982
Creator: Cagle, C.D. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Scientific Report : Development of Transition Metal/ Chalcogen Based Cathode Catalysts for PEM Fuel Cells

Description: The aim of this project was to investigate the potential for using base metal sulfides and selenides as low cost replacements for precious metal catalysts, such as platinum, currently being used in PEM fuel cells. The approach was to deposit thin films of the materials to be evaluated onto inert electrodes and evaluate their activity for the cathode reaction (oxygen reduction) as well as ex-situ structural and compositional characterization. The most active materials identified are CoS2 and the… more
Date: February 29, 2008
Creator: Campbell, Stephen, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Administration of ORNL Research Reactors

Description: Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date: August 20, 1962
Creator: Casto, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

New small angle neutron scattering (SANS) instrument at ORNL using a position sensitive area detector

Description: This paper describes the construction and operation of the small-angle neutron scattering instrument which has been set up at the Oak Ridge Research Reactor at ORNL. Motivation for work on this system to date has been the demonstration of the feasibility of the Borkowski-Kopp position-sensitive area detector and the use of pyrolytic graphite monochromating crystal pairs for small angle neutron scattering research. For a relatively modest cost, a serviceable experimental capability has been achi… more
Date: January 1, 1977
Creator: Child, H. R. & Spooner, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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