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Fission-Product Releases to the Primary System of EBR-II, January 1974-March 1975

Description: Seven releases of fission products occurred in EBR-II from January 1974 to March 1975 - - five from mixed-oxide elements and two from sodium-bonded driver-fuel elements. Four releases were from elements that contained a xenon tag, which aided considerably in locating three of the elements; data from the fourth element allowed estimation of changes of tag composition with reactor exposure. Rapid release of fission from two breached mixed-oxide elements caused the reactor to trip because of incre… more
Date: October 1976
Creator: So, B. Y. C.; Lambert, J. D. B.; Johnson, D. L.; Ebersole, E. R. & Brunson, G. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of the Hydrogen Yield in the Radiolysis of Water by Dissolved Fission Products

Description: Hydrogen from the radiolysis of water by dissolved fission products is stripped from the solution and collected by bubbling carbon dioxide through the solution. Quantitative measurements of the G value for hydrogen show that the yield is essentially the same as would be obtained by external gamma radiolysis of nonradioactive solutions of the same chemical composition. The hydrogen yield can be enhanced by addition of a hydrogen-atom donor, such as formic acid, to the solution. The yield of hydr… more
Date: April 1976
Creator: Sauer, M. C., Jr.; Hart, E. J.; Flynn, K. F. & Gindler, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Branching Fraction in the Radioactive Decay of ⁸⁵mKr

Description: The branching fraction in the decay of the fission product ⁸⁵m-krypton⁸⁵m to the ground state ⁸⁵krypton (10.75 y) was measured relative to the total decay to both ⁸⁵krypton and ⁸⁵Rb. Samples of uranium-235 were highly irradiated in a high-flux reactor and dissolved. ⁸⁵Rb was measured by isotope-dilution mass spectrometry, and the ⁸⁵krypton was counted in GM tubes the counting efficiencies of which were calibrated with a standardized ⁸⁵krypton gas of known disintegration rate. The branching frac… more
Date: February 1980
Creator: Jaffey, A. H.; Steinberg, E. P.; Gindler, J. E.; Gray, J.; Horwitz, E. P.; Hughes, J. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuels for Research and Test Reactors, Status Review: July 1982

Description: A thorough review is provided on nuclear fuels for steady-state thermal research and test reactors. The review was conducted to provide a documented data base in support of recent advances in research and test reactor fuel development, manufacture, and demonstration in response to current US policy on availability of enriched uranium. The review covers current fabrication practice, fabrication development efforts, irradiation performance, and properties affecting fuel utilization, including the… more
Date: December 1982
Creator: Stahl, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Programs Semiannual Progress Report: October 1991-March 1992

Description: This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
Date: November 1993
Creator: Bates, John K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Programs Semiannual Progress Report: April-September 1992

Description: This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April-September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
Date: May 1994
Creator: Bates, John K.; Bradley, C. R.; Buck, E. C.; Dietz, N. L.; Ebert, William L.; Emery, J. W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Theory and Use of GIRAFFE for Analysis of Decay Characteristics of Delayed-Neutron Precursors in an LMFBR

Description: The application of the computer code GIRAFFE (General Isotope Release Analysis For Failed Elements) written in FORTRAN IV is described. GIRAFFE was designed to provide parameter estimates of the nonlinear discrete-measurement models that govern the transport and decay of delayed-neutron precursors in a liquid-metal fast breeder reactor (LMFBR). The code has been organized into a set of small, relatively independent and well-defined modules to facilitate modification and maintenance. The program… more
Date: July 1980
Creator: Gross, Kenny C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Fission-Product Data Assessment

Description: This assessment seeks (1) to determine the most probable chemical compounds formed between fission products and actinides in urania fuels under normal and accident conditions and (2) to identify gaps in knowledge of these fission-product compounds. The ultimate goal of this effort is to develop predictive capability about the behavior of fission products under normal and accident conditions. The relevant thermochemical data have been organized by compound type, the chemical stability of resulta… more
Date: September 1982
Creator: Blackburn, P. E. & Johnson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Methodology for Analysis of Delayed-Neutron Signals

Description: Experimental and analytical techniques have been developed for analysis and characterization of delayed-neutron (DN) signals that can provide diagnostic information to augment data from cover-gas analyses in the detection and identification of breached elements in an LMFBR. Eleven flow-reduction tests have been run in EBR-II to provide base data support for predicting DN signal characteristics during exposed-fuel operation. Results from the tests demonstrate the feasibility and practicability o… more
Date: February 1980
Creator: Gross, K. C.; Strain, R. V. & Fryer, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Applied Physical Chemistry Progress Report, October 1991 - September 1992

Description: This document reports on the work done in applied physical chemistry at the Chemical Technology Division (CMT), Argonne National Laboratory (ANL), in the period October 1991 through September 1992. this work includes research into the process that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor under development at ANL, and the properties of candidate triti… more
Date: December 1993
Creator: Johnson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report for the Light Water Breeder Reactor Proof-of-Breeding Analytical Support Project

Description: The technology of breeding uranium-233 from thorium-232 in a light water reactor is being developed and evaluated by the Westinghouse Bettis Atomic Power Laboratory (BAPL) through operation and examination of the Shippingport Light Water Breeder Reactor (LWBR). Bettis is determining the end-of-life (EOL) inventory of fissile uranium in the LWBR core by nondestructive assay of a statistical sample comprising approximately 500 EOL fuel rods. This determination is being made with an irradiated-fue… more
Date: May 1987
Creator: Graczyk, D. G.; Hoh, J. C.; Martino, F. J.; Nelson, R. E.; Osudar, John & Levitz, Norman M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report

Description: Abstract: "This report describes the results of X-ray diffraction examination of reaction products from a series of experiments performed by Mallinckrodt Chemical Works as an acid in understanding the process of bomb reduction of UF4. UF4 is initially reduced to UF3 by magnesium at 560 C., and subsequently to metal at 600 C. MgF2 from the initial reaction forms a coating on the magnesium which retards the final spontaneous reaction."
Date: May 15, 1953
Creator: Schwartz, C. M. & Vaughan, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Exploratory Scavenging Studies for the Decontamination of Redox Solutions

Description: From introduction: "This report is concerned with exploratory experiments designed to studies the efficiency of a number of scavengers for zirconium and niobium adsorption and to provide preliminary information on the best conditions to employ on the most satisfactory of those scavengers studied, namely Super Filtrol FO. The data in this report include data obtained through October, 1949, and are by no means considered to be final. The investigation is currently being actively continued."
Date: May 1, 1950
Creator: Roake, W. E. & Lowe, C. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Environmental Working Level Monitor

Description: Abstract: "The Environmental Working Level Monitor (EWLM) is an instrument used to automatically monitor airborne Rn-daughter concentrations and the Working Level (WL). It is an ac powered, microprocessor-based instrument with an external inverter provided for dc operation if desired. The microprocessor's control processor unit (CPU) controls the actuation of the detector assembly and processes its output signals to yield the measurements in the proper units. The detectors are fully automated a… more
Date: September 29, 1978
Creator: Keefe, Donald J.; McDowell, William P. & Groer, Peter G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results of UO₂ Diagnositic Tests for Run Beyond Cladding Breach in EBR-2

Description: Pre-defected uranium dioxide fuel elements were irradiated in EBR-II to determine the response of the fission-product-monitoring systems. In particular, the tests were performed to indicate whether the amount of oxide fuel exposed to the primary sodium could be estimated by monitoring, with the fuel-element-rupture detector (FERD), delayed neutrons (DN's) emitted from bromine and iodine isotopes in the sodium. Elements with defect areas of 0.005 and 0.20 cm sq. were irradiated consecutively in … more
Date: 1979
Creator: Strain, R. V. & Lambert, J. D. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EBR-2 Fisson-Product-Source Test No. 1

Description: A fission-product source (FPS) was irradiated in EBR-II to provide data for calibrating the facility's fuel-element rupture detector (FERD), which is a delayed-neutron monitor, and germanium-lithium argon-scanning system (GLASS), a fission-gas-activity monitor. A metal alloy source, Ni-3.2 wt.% uranium, provided quantitative recoil release of the fission-product nuclides. The source alloy, in tubular form, was irradiated as core-region segments of 18 capsules in the FPS subassembly. The irradia… more
Date: August 1978
Creator: Strain, R. V.; Fogle, G. L.; Thresh, H. R.; Heinrich, R. R.; Freyer, R. M.; So, B. Y. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Role of Bubble-Size Equilibration in the Transient Behavior of Fission Gas

Description: An explicit analysis of bubble-size equilibration by volume diffusion has been derived and incorporated into the FRAS2 code. This code was developed for mechanistic analysis of transient fission-gas behavior in LMFBR fuel, but had been limited by the approximation that the time required for bubble-size adjustment, following coalescence or changes in temperature or pressure, was negligible. The equilibration phenomenon is illustrated by several idealized examples. If the fuel temperature rises l… more
Date: 1978?
Creator: Gruber, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Report on the Possible Effects on the Surrounding Population of an Assumed Release of Fission Products into the Atmosphere from a 300 Megawatt Nuclear Reactor Located at Lagoona Beach, Michigan

Description: Report issued by the APDA over studies conducted on the release of radioactive particles near Lagoona Beach, Michigan in 1955. "The possible effects on the surrounding population of a release of fission products at the Lagoona Beach site" (p. 1) are discussed. This report includes tables, maps, and illustrations.
Date: July 1957
Creator: Gomberg, Henry J.; Bassett, Thomas; Velez, Carlos & Donnell, Alton P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculations on U235 Fission Product Decay Chains

Description: Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
Date: May 1952
Creator: Faller, I. L.; Chapman, T. S. & West, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination of ORNL Purex Pilot Plant

Description: From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date: May 5, 1952
Creator: Wood, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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