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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.
Partner: UNT Libraries Government Documents Department

Investigation of Reactivity Anomalies in EBR-II

Description: A data-collection and advisory team was formed to investigate observations of power reactivity decrement (PRD) and reactivity loss rate (RLR) obtained during EBR-II reactor run 74, because both the PRD and RLR were judged to be high during that run. This report describes the efforts to develop a realistic model explaining the reactivity observations for run 74 and presents recommendations for additional diagnostic information in the event of a recurrence of off-normal behavior of reactivity.
This item is restricted from view until June 1, 2076.
Date: June 1976
Creator: Walters, L. C.; Cutforth, D. C.; Forehand, H. M.; Hudman, G. D.; Larson, H. A.; MacFarlane, H. F. et al.
Partner: UNT Libraries Government Documents Department
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Final Safety Analysis Addenda to Hazards Summary Report, Experimental Breeder Reactor II (EBR-II) : Upgrading of Plant Protection System, Volume 1

Description: This report is a compilation of the formal Final Safety Analysis Addenda (FSAA's) to the EBR-II Hazard Summary Report and Addendum that have been prepared in support of certain modifications to the reactor-shutdown-system portion of the EBR-II plant protection system. Each major section is an edited version of the original FSAA for a particular modification and provides a description of the pre - and post -modification system, the rationale for the modification, and required supporting safety a… more
Date: March 1976
Creator: Sackett, J. I. & Gale, N. L.
Partner: UNT Libraries Government Documents Department
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Germanium-Lithium Argon Scanning System (GLASS) : Design and Experience Through 1974

Description: The germanium-lithium argon scanning system (GLASS) was installed in EBR-II to monitor and analyze the gamma activity of the reactor cover gas and the reactor building air. GLASS has the capability to identify and measure 20 or more gamma peaks. Applied to the reactor cover gas, this capability has proven useful in identifying the source of fission-gas leakage from fuel elements. The gamma-peak data can clearly distinguish a carbide-fuel source from an oxide-fuel source and can often help disti… more
Date: July 1976
Creator: Brunson, G. S.
Partner: UNT Libraries Government Documents Department
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Design and Fabrication of the EBR-II Environmental Instrumented Subassembly : Test XX07

Description: The EBR-II environmental instrumented subassembly (EISA), or Test XX07, was designed, fabricated, and irradiated to provide in-core measurements of irradiation conditions. This subassembly contained 57 elements with uranium metal-5 wt.% fissium fuel and four non-fueled elements. It was instrumented with two permanent-magnet flowmeters, 13 coolant thermocouples at various axial and radial locations, 10fuel-centerline thermocouples, and two self-powered detectors. The subassembly was irradiated i… more
Date: 1977
Creator: Gillette, J. L.; Ploncsik, J.; Smaardyk, A.; Walker, D. E.; Filewicz, E. C.; Longnecker, A. A. et al.
Partner: UNT Libraries Government Documents Department
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Studies of Axial-Leakage Simulations for Homogeneous and Heterogeneous EBR-II Core Configurations

Description: When calculations of flux are done in less than three dimensions, leakage-absorption cross sections are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. Since the neutron flux is axially dependent, the leakages, and hence the leakage-absorption cross sections, are also axially dependent. Therefore, to obtain axial flux profiles (or reaction rates) for individual subassemblies, an XY-geometry calculation delineating each subassembly has to be done a… more
Date: August 1985
Creator: Grimm, K. N. & Meneghetti, D.
Partner: UNT Libraries Government Documents Department
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The TRIO Experiment

Description: The TRIO experiment is a test of in-situ tritium recovery and heat transfer performance of a miniaturized solid breeder blanket assembly. The assembly (capsule) was monitored for temperature and neutron flux profiles during irradiation and a sweep gas flowed through the capsule to an analytical train wherein the amounts of tritium in its various chemical forms were determined. The capsule was designed to operate at different temperatures and sweep gas conditions. At the end of the experiment th… more
Date: September 1984
Creator: Clemmer, Robert G.
Partner: UNT Libraries Government Documents Department
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Unavailability Modeling and Analysis of Redundant Safety Systems

Description: Analytical expressions have been developed to estimate the average unavailability of an m-out-of-n (m/n, 1 less than or equal to m less than or equal to n less than or equal to 4) standby safety system of a nuclear power plant. The expressions take into account contributions made by testing, repair, equipment failure, human error, and different testing schemes. A computer code, ICARUS, has been written to incorporate these analytical equations. The code is capable of calculating the average una… more
Date: October 1979
Creator: Argonne National Laboratory. Reactor Analysis and Safety Division.
Partner: UNT Libraries Government Documents Department
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Proceedings of the NEACRP/IAEA Specialists Meeting on the International Comparison Calculation of a Large Sodium-Cooled Fast Breeder Reactor at Argonne National Laboratory on February 7-9, 1978

Description: The results of an international comparison calculation of a large (1250 MWe) LMFBR benchmark model are presented and discussed. Eight reactor configurations were calculated. Parameters included with the comparison were: eigenvalue, k/sub infinity/, neutron balance data, breeding reaction rate ratios, reactivity worths, central control rod worth, regional sodium void reactivity, core Doppler and effective delayed neutron fraction. Ten countries participated in the comparison, and sixteen solutio… more
Date: August 1980
Creator: LeSage, L. G.; McKnight, R. D.; Wade, D. C.; Freese, K. E. & Collins, P. J.
Partner: UNT Libraries Government Documents Department
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Report on the Shearing, Dissolution and Analysis of GRIP-II Rod 79-453 (validation rod). Light Water Breeder Reactor Proof-of-Breeding Analytical Support Project

Description: This report covers the processing and analysis of the fuel-bearing section (M-5138) of an irradiated experimental Light Water Breeder Reactor fuel rod, GRIP-II rod No. 79-453; this section has been designated the Validation Rod. Process steps included precision shearing of the rod into eight comminuted segments, dissolution of the segments, and chemical and radiometric analyses of the resulting solutions. The shearing and dissolution were carried out fully remotely in an existing pilot-scale fa… more
Date: October 1981
Creator: Levitz, Norman M.; Parks, John E.; Winsch, Irvin O.; Meyer, Robert J.; Graczyk, D. G.; Tomlinson, Glen et al.
Partner: UNT Libraries Government Documents Department
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An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II

Description: Recent concerns about the proliferation and diversion of plutonium have lead to reconsideration of Uranium-233/Thorium-232 fuel cycles. Although thorium fuels have been studied earlier, much of that work is incomplete; consequently, additional irradiation studies will be necessary.
Date: 1979?
Creator: Foltman, A. J. & Meneghetti, D.
Partner: UNT Libraries Government Documents Department
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Investigations of Materials Compatibility Relevant to the EBR-II system : FY 1977 and the Transition Period

Description: Report on yearly investigations of components of the EBR-II reactor plant and on out-of-reactor experiments in which materials or techniques are tested before they are used in the EBR-II reactor system.
Date: February 1978
Creator: Longua, K. J.; Ruther, W. E.; Shields, J. A. & Clark, A. F.
Partner: UNT Libraries Government Documents Department
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Summary, Analysis, and Comparison of Data from Experiments with the EBR-II Mark IIB Oscillator Rod

Description: The Mark IIB oscillator rod was used in EBR-II runs 48-55. Data were collected, digitized, and processed by on-line computer analysis, and Fourier analysis was used to obtain frequency-response functions. Feedback frequency-response functions are compared with those obtained by rod-drop experiments and are qualitatively identical. Experimental results are also compared with the EBR-II dynamic simulation computer program, EROS. Through the use of basic neutronic and heat-transfer principles, thi… more
Date: 1977?
Creator: Larson, H. A. & Dean, E. M.
Partner: UNT Libraries Government Documents Department
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Approximations of Gamma Cross Sections for Fast Nuclear Reactors

Description: The report shows a method to approximate a P₁ scattering solution for the flux in a fast reactor, using an isotropic, but not a diagonal-transport-approximation scattering matrix. Presented are flux errors relative to a P₁ solution for different levels of transport approximation in an EBR-II type of core surrounded by a stainless steel reflector. Problems associated with the use of the method are also presented.
Date: 1978?
Creator: Grimm, K. N. & Meneghetti, D.
Partner: UNT Libraries Government Documents Department
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Fast Breeder Reactor Studies

Description: This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast br… more
Date: July 1980
Creator: Till, C. E.; Chang, Y. I.; Kittel, J. H.; Fauske, H. K.; Lineberry, M. J.; Stevenson, M. G. et al.
Partner: UNT Libraries Government Documents Department
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EBR-II Environmental Instrumented Subassembly XX08 : Engineering and Assembly

Description: Subassembly XX08 is a fueled and instrumented subassembly designed primarily for an ongoing program to investigate the thermal-hydraulic core environment within EBR-II under normal and off-normal plant operating conditions. XX08 contains 58-xenon-tagged, EBR-II Mark-II driver-fuel elements. The Mark-II fuel is expected to provide XX08 with an irradiation lifetime three times as great as that attained with its predecessor, XX07, i.e., a 9 versus 2.9% burnup. A burnup of 9 at.% is equivalent to a… more
Date: May 1978
Creator: Smaardyk, A.; Filewicz, E. C.; Longnecker, A. A.; Poloncsik, J.; Tokar, J. V.; Walker, D. E. et al.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Final Safety Analysis Addendum to Hazard Summary Report, Experimental Breeder Reactor No. II (EBR-II): the EBR-II Cover-Gas Cleanup System

Description: This report evaluates abnormal and accident conditions postulated for the EBR-II cover-gas cleanup system (CGCS). Major considerations include loss of CGCS function with a high level of cover-gas activity, loss of the liquid-nitrogen coolant required for removing fission products from the cover gas, contamination of the cover gas from sources other than the reactor, and loss of system pressure boundary. Calculated exposures resulting from the maximum hypothetical accident (MHA) are less than 2%… more
Date: April 1979
Creator: Fryer, R. M.; Monson, L. R.; Price, C. C. & Hooker, D. W.
Partner: UNT Libraries Government Documents Department
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Investigations of Materials Compatibility Relevant to the EBR-2 System : FY 1978

Description: This report is the ninth in a series of yearly reports on investigations of components of the EBR-II reactor plant and out-of-reactor experiments in which materials or techniques are tested before being used in the EBR-II reactor systems. Wide ranges of materials, circumstances, and evaluation techniques are involved. Therefore, each investigation is reported separately.
Date: January 1979
Creator: Longua, K. J.; Shields, J. A.; Ruther, W. E. & Olson, W. H.
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.
Partner: UNT Libraries Government Documents Department
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Failure of a High-Power Pin in a Simulated $3 /s Top Accident: Test E6 Final Report

Description: This report describes the Fuel Dynamics Test E6 and analyzes the test data. A cluster of six fresh FTR-type fuel pins surrounding a previously irradiated pin was tested to failure in a simulated $3/s FFTF accident.
Date: August 1978
Creator: Doerner, R. C.; Stahl, D.; Murphy, W. F. & Stanford, G. S.
Partner: UNT Libraries Government Documents Department
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