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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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Computer-Code Formulation for Three-Dimensional HEXCAN Response Coupled with Internal Hydrodynamics

Description: A procedure is described for the dynamic analysis of a fast-reactor hexagonal subassembly. The internals of the fuel subassembly are treated by an axisymmetric hydrodynamic code REXCO-HT which, among other properties, possesses a model of an MFCI pressure source. The housing of the fuel subassembly is handled by the SADCAT code, which is based on a triangular finite element in three-dimensional space. The code is used to illustrate the discrepancies involved if the hexcan is modeled by a cylind… more
Date: March 1976
Creator: Marchertas, A. H. & Julke, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical Investigation of Certain Aspects of LMFBR Subassembly-Failure Propagation

Description: An analytical investigation of certain problems in the area of subassembly-to-subassembly failure propagation in LMFBR's is described. Existing analyses of the response of the adjacent subassembly duct to mechanical loads are reviewed and summarized, and major uncertainties are identified. Additional analyses of the response of the adjacent subassembly to certain thermal loads are presented in two parts. In the first part, the effect of an external heat flux on duct melting and thermal stresses… more
Date: February 1976
Creator: Marr, William W.; Wang, P. Y.; Misra, B.; Padilla, A. & Crawford, R. M.
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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Simple Conduction Model with Phase Change for Fuel Pin

Description: A simple conduction model with phase change has been developed for the transient analysis of a fuel pin based on average properties and lumped-parameter techniques. The transient behavior of fuel and cladding can be accurately described by simple analytical expressions that agree with conventional numerical approaches for under-cooling transient analysis. If it be assumed that the heat-transfer resistance between the fuel and cladding remains the same for both steady-state and transient periods… more
Date: April 1976
Creator: Chen, W. L.; Ishii, M. & Grolmes, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Examination and Evaluation of in-Reactor Fracture of Shroud Tubes in Mixed-Oxide Fuel Experiment X159

Description: During disassembly and subsequent visual examinations of X159 (a Mark A-19A type of subassembly containing mixed-oxide fuel), 11 of 19 shroud tubes were found fully or partially severed. Several of the capsules within their shroud tubes were distinctly kinked at axial locations near those at which the shroud tubes were severed. The examination also disclosed that the shroud-tube fractures occurred during reactor operations.
Date: June 1977
Creator: Flinn, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Dynamics Loss-of-Flow Test L3 : Final Report

Description: The behavior of FTR-type, mixed-oxide, pre-irradiated, ''intermediate-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 reported here leads to a postulated scenario (sequence and timing) of events in the test. This scenario is presented, together with the calculated timing of events obtained by use of the SAS code.
Date: June 1976
Creator: Fischer, A. K.; Lo, R. K. & Barts, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements

Description: The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date: November 1, 1961
Creator: Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Critical Assembly Safeguards: NDA Methods for Highly Enriched Uranium. Summary Report, October 1978 - September 1979, Volume 3

Description: Nondestructive assay (NDA) methods, principally passive gamma measurements and active neutron interrogation, have been studied for their safeguards effectiveness and programmatic impact as tools for making inventories of highly enriched uranium fast critical assembly fuel plates. It was concluded that no NDA method is the sole answer to the safeguards problem, that each of those emphasized here has its place in an integrated safeguards system, and that each has minimum facility impact.
Date: December 1980
Creator: Bellinger, F. O. & Winslow, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Cycle Programs, Quarterly Progress Report: April-June 1980

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
Date: February 1981
Creator: Steindler, M. J.; Bates, J. K.; Brock, R. E.; Cannon, T. F.; Couture, R. A.; Deeken, P. G. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Programs, Quarterly Progress Report: April-June 1981

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
Date: March 1982
Creator: Steindler, M. J.; Vogler, Seymour; Vandegrift, G. F.; Williams, Jacqueline; Gerding, T. J.; Jardine, L. J. 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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POLYFAIL: A Program for Identification of Multiple Fuel Failures with Gas Tagging

Description: This report describes the development of the computer code POLYFAIL for identification of fuel failures in fast reactors or light-water reactors that use gas tagging. POLYFAIL implements a sophisticated numerical algorithm known as the method of barycentric coordinates. The code can treat problems involving up to four simultaneous tag releases in a tagging system characterized by three independent tag ratios. The sensitivity of the multiple-failure-resolution technique has been optimized by inc… more
Date: 1981
Creator: Gross, Kenny C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Calorimetry and SNM Holdup Measurements, Progress Report: March 1976-August 1976

Description: The calorimetric instrumentation developed at Argonne National Laboratory (ANL) for making nondestructive measurements of the plutonium content of fuel rods is discussed. Measurements with these instruments are relatively fast (i.e., 15 to 20 minutes) when compared to the several hours usually required with more conventional calorimeters and for this reason are called ''fast-response.'' Most of the discussion concerns the One-Meter and the Four-Meter Fuel-Rod Calorimeters and the Analytical Sma… more
Date: February 1977
Creator: Brumbach, S. B.; Finkbeiner, A. M.; Lewis, R. N. & Perry, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THI3D-1: A Computer Program for Steady-State Thermal-Hydraulic Multichannel Analysis

Description: THI3D-1 is an improved version of the THI3D computer program for steady-state, single-phase, thermal-hydraulic multichannel analysis. The program accounts for conservation of mass, energy, and momentum subject to pressure-drop boundary conditions, and leads to a nonlinear multipoint boundary-value problem. Turbulent interchange, radial thermal conduction, and forced flow due to wire wraps or grids between channels are explicitly taken into account. Temperature distributions in the coolant, clad… more
Date: July 1977
Creator: Sha, William T.; Schmitt, R. C. & Lin, E. I. H.
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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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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Summary of Treat Experiments on Oxide Core-Disruptive Accidents

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: February 1979
Creator: Dickerman, Charles Edward; Rothman, Alan B.; Klickman, A. E.; Spencer, B. W. & DeVolpi, Alexander
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A User's Guide for the REBUS-3 Fuel Cycle Analysis Capability

Description: REBUS-3 is a system of programs designed for the fuel-cycle analysis of fast reactors. This new capability is an extension and refinement of the REBUS-3 code system and complies with the standard code practices and interface dataset specifications of the Committee on Computer Code Coordination (CCCC). The new code is hence divorced from the earlier ARC System. In addition, the coding has been designed to enhance code exportability. >Major new capabilities not available in the REBUS-2 code syste… more
Date: March 1983
Creator: Toppel, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Cycle Programs, Quarterly Progress Report: April-June 1982

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
Date: December 1982
Creator: Steindler, M. J.; Bates, J. K.; Cannon, T. F.; Couture, R. A.; Deeken, P. G.; Fagan, J. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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