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Final Report on the Small-Scale Vapor-Explosion Experiments Using a Molten NaCl-H2O System

Description: Vapor explosions were produced by injecting small quantities of water into a container filled with molten sodium chloride. Minimum explosion efficiencies, as evaluated from reaction-impulse measurements, were relatively large. Subsurface movies showed that the explosions resulted from a two-step sequence: an initial bulk-mixing phase in which the two liquids intermix on a large scale, but remain locally separated by an insulating gas-vapor layer; and a second step, immediately following breakdo… more
Date: April 1976
Creator: Anderson, R. P. & Bova, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Summary Report of Fuel-Dynamics Tests H2 and E4

Description: Results of two failure experiments using LMFBR-type fuel during simulated unprotected transient overpower accidents are reported and analyzed. In both experiments, a single fresh fuel pin in a Mark0IIA loop was subjected to a temperature-limited, step-reactivity irradiation in the TREAT reactor. Total energy was 490 MJ in Test H2 and in Test E4.
Date: February 1976
Creator: Doerner, R. C.; Rothman, A. B.; De Volpi, A.; Dickerman, Charles Edward; Deitrich, L. W.; Stahl, D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Xenon-Tagging in Production of EBR-II Mark II Driven-Fuel Elements

Description: About 1200 Mark II driver-fuel elements were xenon-tagged to facilitate qualification for irradiation of Mark II fuel manufactured at ANL-West. Tagging equipment was designed and developed. In this equipment, the plenum in a fuel-element jacket was evacuated then filled with xenon to a predetermined pressure. The equipment design allows tagging and element fabrication to proceed normal rates for production of fuel elements. A Kr-85 tracer in the xenon-tag gas verified by gamma counting the adeq… more
Date: March 1976
Creator: Wilkes, C. W.; Ryan, M. J.; Laug, M. T. & Fryer, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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U-Pu-Zr Metal Alloy: a Potential Fuel for LMFBR's

Description: This report critically reviews the available information pertinent to the potential use of uranium-plutonium-zirconium alloy fuels clad with stainless steel in LMFBR's. The areas considered include breeding potential, burnup potential, thermal performance, fuel fabricability, fuel reprocessing, and safety considerations. Because information on uranium-plutonium-zirconium alloys is limited, wide use is made of experience with EBR-II metallic driver fuel to infer advantages and limitations of ura… more
Date: November 1975
Creator: Walter, C. M.; Golden, G. H. & Olson, N. J.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRTR second generation shim assembly

Description: From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date: November 1964
Creator: Rasmussen, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and Verification of the LIFE-GCFR Computer Code for Predicting Gas-Cooled Fast-Reactor Fuel-Rod Performance

Description: The fuel-pin modeling code LIFE-GCFR has been developed to predict the thermal, mechanical, and fission-gas behavior of a Gas-Cooled Fast Reactor (GCFR) fuel rod under normal operating conditions. It consists of three major components: thermal, mechanical, and fission-gas analysis. The thermal analysis includes calculations of coolant, cladding, and fuel temperature; fuel densification; pore migration; fuel grain growth; and plenum pressure. Fuel mechanical analysis includes thermal expansion, … more
Date: December 1980
Creator: Hsieh, T. C.; Billone, Michael C. & Rest, J.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Program for Development and Evaluation of Nondestructive Assay Techniques for Plutonium Holdup

Description: An outline is presented for an experimental program to develop and evaluate nondestructive assay techniques applicable to holdup measurement in plutonium-containing fuel fabrication facilities. The current state-of-the-art in holdup measurements is reviewed. Various aspects of the fuel fabrication process and the fabrication facility are considered for their potential impact on holdup measurements. The measurement techniques considered are those using gamma-ray counting, neutron counting, and t… more
Date: May 1977
Creator: Brumbach, S. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRANS4 : a Computer Code Calculation of Solid Fuel Penetration of a Concrete Barrier

Description: The computer code, TRANS4, models the melting and penetration of a solid barrier by a solid disc of fuel following a core disruptive accident. This computer code has been used to model fuel debris penetration of basalt, limestone concrete, basaltic concrete, and magnetite concrete. Sensitivity studies were performed to assess the importance of various properties on the rate of penetration. Comparisons were made with results from the GROWS II code.
Date: July 1980
Creator: Ono, C. M.; Kumar, R. & Fink, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Study, Isotopic Safeguards Techniques (IST), LMFBR Fuel Cycles

Description: This memorandum presents the preliminary results of the effort to investigate the applicability of isotope correlation techniques (ICT), formulated for the LWR system, to the LMFBR fuel cycle. The detailed isotopic compositional changes with burnup developed for the CRBR was utilized as the reference case. This differs from the usual LMFBR design studies in that the core uranium is natural uranium rather than depleted. Nevertheless, the general isotopic behavior should not differ significantly … more
Date: June 1980
Creator: Persiani, P. J. & Kroc, T. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Effect of Pressure on the Transient Swelling Rate of Oxide Fuel

Description: An analysis of the transient swelling rate of oxide fuel, based on fission-gas bubble conditions calculated with the FRAS3 code, has been developed and implemented in the code. The need for this capability arises in the coupling of the FRAS3 fission-gas analysis code to the FPIN fuel-pin mechanics code. An efficient means of closely coupling the calculations of swelling strains and stresses between the modules is required. The present analysis provides parameters that allow the FPIN calculation… more
Date: April 1982
Creator: Gruber, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Status and Development Potential of Plate-Type Fuels for Research and Test Reactors

Description: A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins… more
Date: March 1979
Creator: Stahl, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Di-n-Amyl-n-Amylphosphonate and Tricaprylmethylammonium Nitrate as Potential Extractants for Reprocessing Th-U Fuels

Description: Both 2F di-n-amyl-n-amylphosphonate in n-dodecane (DA(AP)-DD) and 0.77F tricaprylmethylammonium nitrate in Aromatic 100 (TCMA.NO/sub 3/-AR100) extract uranium and thorium into relatively concentrated organic solutions. Countercurrent-flow tests with each extractant have demonstrated effective uranium-thorium separations by selective stripping from the organic phase. Both extractants offer advantageous alternatives to tributylphosphate (Thorex) in reprocessing irradiated mixed ThO2-UO2 fuels. Fo… more
Date: September 1979
Creator: Diamond, H.
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
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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Leaching Action of EJ-13 Water on Unirradiated UO₂ Surfaces under Unsaturated Conditions at 90 C : Interim Report

Description: A set of experiments, based on the application of the Unsaturated Test method to the reaction of uranium dioxide with EJ-13 water, has been conducted over a period of 182.5 weeks. One half of the experiments have been terminated, while one half are still ongoing. Solutions that have dripped from uranium dioxide specimens have been analyzed for all experiments, while the reacted uranium dioxide surfaces have been examined for only the terminated experiments. A pulse of uranium release from the u… more
Date: July 1991
Creator: Wronkiewicz, D. J.; Bates, John K.; Gerding, Thomas J.; Veleckis, Ewald; Tani, B. & Hoh, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Notes on Evaporation of Target Materials

Description: Abstract: "The general utility of vacuum evaporated films is discussed. The characteristics that makes this technique most useful are the uniformity of the films, the easy control of their thickness over a large range, and the adaptability of the system to different metals and compounds. The design of a vacuum evaporator should provide adequate pumping speed, cooling of components, filament heater supply, and general flexibility and adaptability of the components to different materials. The des… more
Date: March 1953
Creator: Northrop, J. A. & Stokes, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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F1 Phenomenological Test on Fuel Motion : Final Report

Description: TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothetical loss-of-flow accident. Fuel and fuel-boundary conditions in an LMFBR subassembly following sodium voiding and dryout under loss-of-flow conditions are simulated in each F-series test. Simulation is achieved with a single fuel element surrounded by an annular nuclear-heated wall in a dry (no sodium) test capsule. The area inside the heated wall was selected to represent the area inside the p… more
Date: May 1978
Creator: Argonne National Laboratory. Reactor Analysis and Safety Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Autoradiography as a Safeguards Inspection Technique for Unirradiated LWR Fuel Assemblies

Description: A nondestructive autoradiographic method is described which can provide a verification that rods in the interior of unirradiated LWR fuel assemblies contain low-enriched uranium. Sufficient absorber must be used to reduce contributions to image density by beta radiation from uranium-238 daughters. When appropriate absorbers are used, the density of the image of a uranium-containing fuel rod is proportional to the uranium-235 enrichment in that rod. Exposure times as short as 1.5 hours can be ac… more
Date: May 1978
Creator: Brumbach, S. B. & Perry, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Portable Calorimeter System for Nondestructive Assay of Mixed-Oxide Fuels

Description: Calorimetric assay provides a precise, nondestructive method to determine sample plutonium content based on the heat emitted by decaying radionuclides. This measurement, in combination with a gamma-spectrometer analysis of sample isotopic content, yields the total sample plutonium mass. The technique is applicable to sealed containers and is essentially independent of sample matrix configuration and elemental composition. Conventional calorimeter designs employ large water-bath heat sinks and l… more
Date: 1978
Creator: Roche, C. T.; Perry, R. B.; Lewis, R. N.; Jung, E. A. & Haumann, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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