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Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%)

Description: Biaxial creep-rupture tests were conducted on 12 prototypic GCFR fuel-cladding specimens at 650 deg C and a nominal hoop stress of 241.3 MPa. All test specimens were fabricated from 20% cold-worked Type 316 stainless steel tubes that were ribbed on the outer surface by mechanical grinding or electro-chemical etching. Test variables included specimen length and the presence or absence of weld-reinforcing end collars.
Date: November 1977
Creator: Yaggee, F. L.; Purohit, A.; Grajek, W. J. & Poeppel, R. B.
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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Use of Krypton-85 for the Detection of Pinhole Failures in GCFR Cladding

Description: Radioactive krypton-85 is used as a tracer to detect pinhole failures in GCFR cladding. High-purity helium (99.99% pure) that contains 0.3 ppm krypton-85 is used to pressurize the tubular test specimens, and a Geiger-Mueller counter is used to detect the krypton-85 in the helium environmental gas as it leaves the test chamber. Under the least favorable conditions of temperature and specimen pressure, it is estimated that the smallest pinhole failure that could be detected within 60 sec would ha… more
Date: May 1976
Creator: Yaggee, F. L.; Purohit, A. & Poeppel, R. B.
Partner: UNT Libraries Government Documents Department
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Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant

Description: Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date: October 5, 1962
Creator: Miskell, R. V.
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.
Partner: UNT Libraries Government Documents Department
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Neutron-Induced Helium Implantation in GCFR Cladding

Description: The neutron-induced implantation of helium atoms on the exterior surfaces of the cladding of a prototypic gas-cooled fast reactor (GCFR) has been investigated analytically. A flux of recoil helium particles as high as 4.2 x 10¹⁰ He/cm sq.s at the cladding surface has been calculated at the peak power location in the core of a 300-MWe GCFR. The calculated profile of the helium implantation rates indicates that although some helium is implanted as deep as 20 microns, more than 99% of helium parti… more
Date: October 1980
Creator: Yamada, H.; Poeppel, R. B. & Sevy, R. H.
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
Partner: UNT Libraries Government Documents Department
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Calculations of Stresses in GCFR Cladding under Normal Operating Conditions

Description: A modified version of the LIFE-III code, LIFE-GCFR, and classical stress-analysis techniques have been used to calculate the stresses in the GCFR cladding under normal reactor operating conditions. Several types of loadings on the cladding that occur during normal operation have been considered. These include fuel-cladding mechanical interaction, thermal stresses induced by radial and axial temperature gradients, and swelling gradient-induced stresses. The combined and individual effects of the… more
Date: November 1979
Creator: Liu, Yung Y.; Hsieh, T. C. & Billone, Michael C.
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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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.
Partner: UNT Libraries Government Documents Department
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The Design Study of Fluid Engine Power Systems

Description: From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date: April 12, 1963
Creator: Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
Partner: UNT Libraries Government Documents Department
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GCRE Critical-Assembly Studies

Description: This report follows critical-assembly studies made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiments.
Date: September 10, 1958
Creator: Dingee, David A.; Ballowe, William C.; Klingensmith, Raymond W.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department
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A Conceptual Study of a 100 kw Gas Cooled Reactor Power Plant for a Remote Location

Description: From introduction: This report details the conceptual design of a 100 kw gas cooled reactor power plant of the type that would satisfy the electrical and space heating load of the Air Force distant early warning stations and might find application at other remote bases.
Date: May 31, 1955
Creator: Frankfort, J. H. & Thompson, W. I.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Advanced Converter Reactors

Description: From foreword: This report is an overall assessment of the technical status and economic potential of advanced converters and breeders, the role of thorium, various reactor fuel cycles, and a systems analysis of the future nuclear-electric power complex.
Date: April 1969
Creator: Advanced Converter Task Force
Partner: UNT Libraries Government Documents Department
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Rotating Machinery for Gas-Cooled Reactor Application

Description: From foreword: Representatives from various organizations met to discuss progress in the development of rotating machinery for gas-cooled reactors. The equipment covered included main blowers, shaft seals, gas turbines, gas bearing compressors, and other types of special compressors for reactor or experimental applications.
Date: June 1962
Partner: UNT Libraries Government Documents Department
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Development of Fueled Graphite Containing Pyrolytic-Carbon Coated Carbide Particles for Nonpurged, Gas-Cooled Reactor Systems

Description: Abstract: Progress is reported in several areas of development of fueled graphite containing coated particles for nonurged gas-cooled reactor systems. The sol-gel process has been modified for making spherical particles of both thorium-uranium carbide and thorium-uranium oxide suitable for coating. Equipment has been assembled and methods have been developed for deposition of pyrolytic-carbon coating under well-controlled conditions. Damage to coated particles during fabrication into a graphi… more
Date: November 1963
Creator: Carlsen, F. L., Jr.; Bomar, E. S. & Harms, W. O.
Partner: UNT Libraries Government Documents Department
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Development of Iron-Aluminum Base Alloy for Gas Cooled Reactor Components: Final Report

Description: From summary: Description of an iron-aluminum-chromium alloy, DB-2, used as the starting point of a program initiated to develop an iron-aluminum base alloy for cladding gas-cooled reactor core components. Secondary aims were to gain knowledge of fuel element fabric-ability, radiation effects and acid solubility of iron-aluminum base alloys.
Date: April 1959
Creator: Tate, Frank
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Marine Nuclear Power Plant: Interim Report. Project 16

Description: From preface: The principal portion of this report is the scientific and engineering description of a novel reactor and power-plant scheme which was proposed by General Atomic in response to an invitation of the Maritime Administration.
Date: January 25, 1957
Creator: Thompson, W. I.; Adler, F.; Case, K.; Bond, W. H.; Creutz, E. C.; Hale, E. A. et al.
Partner: UNT Libraries Government Documents Department
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Prestressed Concrete Reactor Vessel Model 1

Description: From introduction: The goal of engineers associated with nuclear power plants is the achievement of safe plants with low generating costs.One possible means of lowering costs is to increase the power generating capability for a single generating unit. To accomplish this, the sizes of nuclear reactors have been increased.
Date: October 25, 1966
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of the Helium-Argon System

Description: A semi-empirical relation for the thermal conductivity of helium-argon gas mixtures is suggested. The analyses used in support of the proposed conductivity relations are based on low-temperature (T < 800 degrees C) thermal conductivity data for helium, argon and helium-argon mixtures. The report is a compilation of available data and theories, and does not contain any new experimental results. With the approach presented here, one should be able to predict thermal conductivities of helium-argon… more
Date: February 1979
Creator: Purohit, A. & Moszynski, Jerzy R.
Partner: UNT Libraries Government Documents Department
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Reactor Physics Studies in the GCFR Phase III Critical Assembly

Description: The third phase of the gas cooled fast reactor (GCFR) program, ZPR-9 Assembly 30, is based on a multi-zoned core of PuO2-UO2 with radial and axial blankets of uranium dioxide. Studies performed in this assembly will be compared to the previous phases of the GCFR program and will help to define parameters in this power-flattened demonstration plant-type core. Measurements in the Phase III program included small sample reactivity worths of various materials, central reaction rates and reaction ra… more
Date: March 1980
Creator: Argonne National Laboratory. Applied Physics Division.
Partner: UNT Libraries Government Documents Department
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