Technical Report Archive & Image Library (TRAIL) - 2,261 Matching Results

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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.
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.
Partner: UNT Libraries Government Documents Department
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Simulation Test Approach to the Evaluation and Comparison of Unconstrained Nonlinear Optimization Algorithms

Description: A simulation test technique was developed to evaluate and compare unconstrained nonlinear optimization computer algorithms. Descriptions of the test technique, test problems, computer algorithms tested, and test results are provided.
Date: 1976
Creator: Hillstrom, Kenneth E.
Partner: UNT Libraries Government Documents Department
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SYN3D: a Single-Channel, Spatial Flux Synthesis Code for Diffusion Theory Calculations

Description: This report is a user's manual for SYN3D, a computer code which uses single-channel, spatial flux synthesis to calculate approximate solutions to two- and three-dimensional, finite-difference, multi-group neutron diffusion theory equations. SYN3D is designed to run in conjunction with any one of several one- and two-dimensional, finite-difference codes (required to generate the synthesis expansion functions) currently being used in the fast reactor community. The report describes the theory and… more
Date: 1976
Creator: Adams, C. H.
Partner: UNT Libraries Government Documents Department
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Urban Design and Public Exposure to Carbon Monoxide

Description: In protecting the public from the risk of exposure to damaging levels of carbon monoxide, two approaches are possible; the pollutant's concentration may be lowered by traffic management measures or the public's rate of exposure may be reduced through urban design features. The present emphasis on traffic management stresses improving the flow and reducing the level of traffic, goals that are extremely costly to achieve in downtown areas. This paper examines ways to reduce risk of exposure by th… more
Date: 1976
Creator: Santini, Danilo J.
Partner: UNT Libraries Government Documents Department
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Study on Flow Instabilities in Two-Phase Mixtures

Description: Various mechanisms that can induce flow instabilities in two-phase flow systems are reviewed and their relative importance discussed. In view of their practical importance, the density-wave instabilities have been analyzed in detail based on the one-dimensional two-phase flow formulation. The dynamic response of the system to the inlet flow perturbations has been derived from the model; thus the characteristic equation that predicts the onset of instabilities has been obtained. The effects of v… more
Date: March 1976
Creator: Ishii, M.
Partner: UNT Libraries Government Documents Department
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Explosive Interaction of Molten UO2 and Liquid Sodium

Description: The interim report presented describes a continuation of the work reported in ANL-7890, Interaction of Sodium with Molten Uranium dioxide and Stainless Steel Using a Dropping Mode of Contact. In the current study, sodium was injected into a pool of molten uranium dioxide. The experiment consistently produced vapor explosions, both with the injection nozzle above and beneath the surface of the uranium dioxide. Although the efficiency of the conversion of thermal to mechanical energy was small (d… more
Date: March 1976
Creator: Armstrong, D. R.; Goldfuss, G. T. & Gebner, R. H.
Partner: UNT Libraries Government Documents Department
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Effects of Possible Compression Loading of EBR-II Subassemblies Due to Irradiation-Induced Swelling and Changes in Reactor Environment

Description: A condition of compression loading could possibly occur to a subassembly as a result of large length changes to irradiation-induced swelling and thermal expansion. The effects of axial compression loading on EBR-II experimental and driver-fuel subassemblies were evaluated. Compression tests that were performed on the slotted top fixture of a subassembly showed that a force of 2100 lb at 900 degrees F would close the slot enough so that the core-gripper blade would not fit into the slot. Such a … more
Date: August 1975
Creator: Longua, K. J.; Flinn, J. E.; Koenig, J. F. & Walters, L. C.
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.
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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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.
Partner: UNT Libraries Government Documents Department
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Plutonium Safety Training Course

Description: This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four prope… more
Date: March 1976
Creator: Moe, H. J.
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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High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: January-March 1976

Description: Quarterly report describing the research and management effort of Argonne National Laboratory's program on lithium/metal sulfide batteries during the period January-March 1976. These batteries are being developed for energy storage on utility networks and for electric-vehicle propulsion. The present cells are vertically oriented, piismatic cells with a central positive electrode of FeS or FeS; and two facing negative electrodes of lithium-aluminum alloy, and an electrolyte of molten LiCl-KC1. T… more
Date: May 1976
Creator: Nelson, P. A.; Ivins, R. O.; Yao, N. P.; Battles, J. E.; Chilenskas, A. A.; Gay, E. C. et al.
Partner: UNT Libraries Government Documents Department
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Experimental Study of the Neutronics of the First Gas Cooled Fast Reactor Benchmark Assembly (GCFR Phase 1 Assembly)

Description: The Gas Cooled Fast Reactor (GCFR) Phase I Assembly is the first in a series of ZPR-9 critical assemblies designed to provide a reference set of reactor physics measurements in support of the 300 MW(e) GCFR Demonstration Plant designed by General Atomic Company. The Phase I Assembly was the first complete mockup of a GCFR core ever built. A set of basic reactor physics measurements were performed in the assembly to characterize the neutronics of the assembly and assess the impact of the neutron… more
Date: December 1976
Creator: Bhattacharyya, S. K.
Partner: UNT Libraries Government Documents Department
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One-Dimensional Cladding-Relocation Model for Fast-Reactor Loss-of-Flow Accidents

Description: The motion and location of the molten-cladding during an unprotected loss-of-flow accident in liquid metal fast breeder reactors are important because of the effects on the reactivity and the subsequent fuel motion. The present study analyzes the cladding-relocation problem based on a single-channel film-flow model and a simple thermal transient model for fuel pins. The motion of molten cladding induced by sodium-vapor streaming undergoes initial rapid upward acceleration, slowing down, flow re… more
Date: March 1976
Creator: Ishii, M.; Chen, W. L. & Grolmes, M. A.
Partner: UNT Libraries Government Documents Department
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ANL/HIWAY: an Air Pollution Evaluation Model for Roadways

Description: This report describes a computer program, called ANL/HIWAY, for estimating air quality levels of nonreactive pollutants produced by vehicular sources. It is valid for receptors at distances of tens to hundreds of meters, at an angle, downwind of the roadway, in relatively uncomplicated terrain. It may be used by planners to analyze the effects of a proposed roadway on adjacent air quality. The ANL/HIWAY model expands the evaluation capabilities of the EPA/HIWAY dispersion model. This report als… more
Date: December 1976
Creator: Concaildi, George A.; Cohen, Alan S. & King, Richard F.
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.
Partner: UNT Libraries Government Documents Department
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Risk-assessment methodology for fast breeder reactors

Description: The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly with respect to their applicability for risk assessment of future commercial fast breeder reactors. All methods are based on the calculation of accident consequences for relatively few accident scenarios. The role and general impact of uncertainties in fast-reactor accident analysis are discussed. The discussion shows the need for improvement of the methodology. A generalized and improved risk-ass… more
Date: April 1976
Creator: Ott, Karl O.
Partner: UNT Libraries Government Documents Department
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Application of Frequency-Modified Life Approach to the Low-Cycle Fatigue Behavior of Type 304 Stainless Steel

Description: The application of the frequency-modified life equation to fatigue life prediction has been critically examined using the extensive fatigue data generated for Type 304 stainless steel at 1100 degrees F under a variety of cyclic-loading conditions. The parameters that enter into the frequency-modified life equation vary with strain rate and show a transition coinciding with the frequency of cycling at which a change in the fracture appearance from predominantly transgranular to predominantly int… more
Date: May 1976
Creator: Maiya, P. S. & Majumdar, S.
Partner: UNT Libraries Government Documents Department
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Experimental and Analytical Study of the Sputtering Phenomena

Description: An experimental apparatus was constructed to examine the heat-transfer characteristics of a sputtering front. In the present study, a heat source of sufficient intensity was located immediately below the sputtering front, which prevented its downward progress, thus permitting detailed measurements of steady-state surface temperatures throughout a sputtering front. A two-dimensional analytical model was developed to describe a stationary sputtering front where the wet-dry interface corresponds t… more
Date: March 1976
Creator: Howard, Paul A.
Partner: UNT Libraries Government Documents Department
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Reactor Physics Studies in the Engineering Mockup Critical Assembly of the Fast Test Reactor

Description: Reactor physics studies in the Engineering Mockup Critical (EMC) assembly of the Fast Test Reactor (FTR) facility are reported. The study included measurements of the neutron spectrum, Doppler effect, sodium-void worth, reaction rates, subassembly worths, material replacement worths, and FTR control, safety and shim rod worths. Each of these physics studies were made in a clean plutonium (low-Pu-240) fuel composition environment and a dirty plutonium (high-Pu-240) fuel composition environment. … more
Date: July 1976
Creator: Pond, R. B.
Partner: UNT Libraries Government Documents Department
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