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Gas Reactor International Cooperative Program. Interim report. Construction and operating experience of selected European Gas-Cooled Reactors

Description: The construction and operating experience of selected European Gas-Cooled Reactors is summarized along with technical descriptions of the plants. Included in the report are the AVR Experimental Pebble Bed Reactor, the Dragon Reactor, AGR Reactors, and the Thorium High Temperature Reactor (THTR). The study demonstrates that the European experience has been favorable and forms a good foundation for the development of Advanced High Temperature Reactors.
Date: September 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Overview of US fast-neutron facilities and testing capabilities

Description: Rather than attempt a cataloging of the various fast neutron facilities developed and used in this country over the last 30 years, this paper will focus on those facilities which have been used to develop, proof test, and explore safety issues of fuels, materials and components for the breeder and fusion program. This survey paper will attempt to relate the evolution of facility capabilities with the evolution of development program which use the facilities. The work horse facilities for the br… more
Date: January 1, 1982
Creator: Evans, E.A.; Cox, C.M. & Jackson, R.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design and operation of a rapid thermal transient component testing sodium loop

Description: A specific problem developed during the design of an on-line sampling system for the Sodium Loop Safety Facility fast breeder reactor experiments. Rapid fluctuations in the sodium temperature, caused by reactor operation and shutdown, exposed the system components to conditions that could result in fatigue failure. A component test loop was designed and built at the Idaho National Engineering Laboratory to allow experimental qualification of component integrity. This paper outlines test system … more
Date: April 16, 1984
Creator: Crandall, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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United States Department of Energy breeder reactor staff training domestic program

Description: Two US DOE projects in the Pacific Northwest offer unique on-the-scene training opportunities at sodium-cooled fast-reactor plants: the Fast Flux Test Facility (FFTF) near Richland, Washington, which has operated successfully in a wide range of irradiation test programs since 1980; and the Experimental Breeder Reactor II (EBR-II) near Idaho Falls, Idaho, which has been in operation for approximately 20 years. Training programs have been especially designed to take advantage of this plant experi… more
Date: January 1, 1984
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Conclusions Drawn From Subcritical Multiplication Results in ZPPR

Description: Modified source multiplication (MSM) has been investigated as a measurement technique for several LMFBR designs in the 1000 MWt class. This investigation has been based on the results of hundreds of measurements in ZPPR as well as on detailed analysis of some of the components of the method. The results of this study have special significance for critical-experiment planning and for the use of ex-vessel detectors in operating LMFBRs. The calculated factors that are applied in the MSM technique … more
Date: January 1, 1978
Creator: Carpenter, S. G.; McFarlane, H. F.; Lineberry, M. J. & Beck, C. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of the TREAT loss-of-flow tests L6 and L7 using SAS3D

Description: The TREAT loss-of-flow tests L6 and L7 have been analyzed using the SAS3D accident analysis code. The impetus for the analysis was the need for experimentally supported fuel motion modeling in whole core accident studies performed in support of licensing of the Clinch River Breeder Reactor Project. The input prescription chosen for the SAS3D/SLUMPY fuel motion model gave reasonable agreement with the test results. Tests L6 and L7, each conducted with a cluster of three fuel pins, were planned t… more
Date: January 1, 1985
Creator: Morris, E. E.; Simms, R. & Gruber, E. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Theory, design, and operation of liquid metal fast breeder reactors, including operational health physics

Description: A comprehensive evaluation was conducted of the radiation protection practices and programs at prototype LMFBRs with long operational experience. Installations evaluated were the Fast Flux Test Facility (FFTF), Richland, Washington; Experimental Breeder Reactor II (EBR-II), Idaho Falls, Idaho; Prototype Fast Reactor (PFR) Dounreay, Scotland; Phenix, Marcoule, France; and Kompakte Natriumgekuhlte Kernreak Toranlange (KNK II), Karlsruhe, Federal Republic of Germany. The evaluation included extern… more
Date: October 1, 1985
Creator: Adams, S. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Instrument response during overpower transients at TREAT

Description: A program to empirically analyze data residuals or noise to determine instrument response that occurs during in-pile transient tests is out-lined. As an example, thermocouple response in the Mark III loop during a severe overpower transient in TREAT is studied both in frequency space and in real-time. Time intervals studied included both constant power and burst portions of the power transient. Thermocouple time constants were computed. Benefits and limitations of the method are discussed.
Date: January 1, 1982
Creator: Meek, C. C.; Bauer, T. H.; Hill, D. J.; Froehle, P. H.; Klickman, A. E.; Tylka, J. P. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fuel-cycle costs for alternative fuels

Description: This paper compares the fuel cycle cost and fresh fuel requirements for a range of nuclear reactor systems including the present day LWR without fuel recycle, an LWR modified to obtain a higher fuel burnup, an LWR using recycle uranium and plutonium fuel, an LWR using a proliferation resistant /sup 233/U-Th cycle, a heavy water reactor, a couple of HTGRs, a GCFR, and several LMFBRs. These reactor systems were selected from a set of 26 developed for the NASAP study and represent a wide range of … more
Date: January 1, 1980
Creator: Rainey, R.H.; Burch, W.D.; Haire, M.J. & Unger, W.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Pump, sodium, inducer, intermediate size (ISIP) (impeller/inducer/diffuser retrofit)

Description: This specification defines the requirements for the Intermediate-Size Inducer Pump (ISIP), which is to be made by replacing the impeller of the FFTF Prototype Pump with a new inducer, impeller, diffuser, seal, and necessary adapter hardware. Subsequent testing requirements of the complete pump assembly are included.
Date: April 21, 1978
Creator: Paradise, D.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of gamma-ray heating characterization in LMFBR

Description: Efforts to define gamma-ray heating in Liquid Metal Fast Breeder Reactor (LMFBR) environments have been surveyed. Emphasis is placed on both current practice for the Experimental Breeder Reactor-II (EBR-II) and future needs of the Fast Flux Test Facility (FFTF). Experimental and theoretical work are included in this preliminary survey for both high and low power environments. Current ''state-of-the-art'' accuracies and limitations are assessed. On this basis, it is concluded that a broad and su… more
Date: November 1, 1975
Creator: Gold, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modeling and analysis of the unprotected loss-of-flow accident in the Clinch River Breeder Reactor

Description: The influence of fission-gas-driven fuel compaction on the energetics resulting from a loss-of-flow accident was estimated with the aid of the SAS3D accident analysis code. The analysis was carried out as part of the Clinch River Breeder Reactor licensing process. The TREAT tests L6, L7, and R8 were analyzed to assist in the modeling of fuel motion and the effects of plenum fission-gas release on coolant and clad dynamics. Special, conservative modeling was introduced to evaluate the effect of … more
Date: January 1, 1985
Creator: Morris, E. E.; Dunn, F. E.; Simms, R. & Gruber, E. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Automated start-up of EBR-II: A preview

Description: Oak Ridge National Laboratory (ORNL) and Argonne National Laboratory (ANL) are undertaking a joint project to develop control philosophies, strategies, and algorithms for computer control of the start-up mode of the Experimental Breeder Reactor II (EBR-II). The major objective of this project is to show that advanced liquid-metal reactor (LMR) plants can be operated from low power to full power using computer control. Development of an automated control system with this objective in view will h… more
Date: January 1, 1989
Creator: Kisner, R. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Large EM pump program review. [Annular linear induction]

Description: Objectives were to review the Annular Linear Induction Pump (ALIP) concept and program status, determine the desirability for such a concept for large scale plant Main Heat Transport systems, and establish the extent of interest and support for preceeding with development.
Date: January 23, 1976
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Liquid-metal pumps for large-scale breeder-reactor plant (prototype pump)

Description: This report presents the recommended pump design for use in Large Scale Liquid Metal Fast Breeder Reactor plants. The base design for the pump will circulate 127,000 GPM of liquid sodium at temperatures up to 850/sup 0/F and with a total discharge head at the design point of 500 feet Na with an impeller that is 40 feet below the sodium seal. The pump design is predicated on developing an impeller design which will have a suction specific speed (S/sub n/) of about 20,000 with 20 feet NPSH availa… more
Date: July 1, 1976
Creator: Lindsay, M. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improved algorithms for the calculation of resolved resonance cross sections with applications to the structural Doppler effect in fast reactors

Description: Motivated by a need for an economical yet rigorous tool which can address the computation of the structural material Doppler effect, an extremely efficient improved RABANL capability has been developed utilizing the fact that the Doppler broadened line shape functions become essentially identical to the natural line shape functions or Lorentzian limits beyond about 100 Doppler widths from the resonance energy, or when the natural width exceeds about 200 Doppler widths. The computational efficie… more
Date: October 1, 1980
Creator: Hwang, R. N.; Toppel, B. J. & Henryson II, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast reactor operation in the United States

Description: Of the many American facilities dedicated to fast reactor technology, six qualify as liquid-metal-cooled fast reactors. All of these satisfy the following criteria: an unmoderated neutron spectrum, highly enriched fuel material, substantial heat production, and the use of a liquid metal coolant. These include the following: EBR-I Clementine, LAMPRE, EBR-II, EFFBR, and SEFOR. Collectively, these facilities encompassed all of the more important features of liquid-metal-cooled fast reactor technol… more
Date: January 1, 1978
Creator: Smith, R. R. & Cissel, D. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SLSF local fault safety experiment P4: summary and conclusions. [Sodium Loop Safety Facility]

Description: Sodium Loop Safety Facility (SLSF) experiment P4 in ETR was performed to investigate the consequences of an upper-bound or worse-than-worst case local fault configuration. P4 was intended to bound the consequences of credible subassembly faults by ejecting molten fuel into a 37-pin bundle of full-length Fast Test Reactor (FTR)-type pins and failing fuel with the potential for further cladding and fuel-pin damage. In addition to ejecting a large amount of molten fuel at or near full power, exper… more
Date: January 1, 1985
Creator: Thompson, D. H.; Ragland, W. A.; Holland, J. W.; Dever, D. J.; Braid, T. H.; Baldwin, R. D. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Coded aperture imaging of reactor illuminated LMFBR fuel pins

Description: As a part of Sandia Laboratories program to study simulated core disruptive accidents in reactor safety research, a fuel motion detection system based on coded aperture imaging is being developed. Until the experiments reported here were conducted it was not known whether either of two important questions could be properly answered. First, could an actual fuel pin illuminated by a reactor be imaged with a coded aperture and an active detector system with acceptable frame rates and spatial resol… more
Date: January 1, 1977
Creator: Kelly, J. G. & Stalker, K. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Hydrodynamic analysis of the LMFBR prompt burst excursion (PBE) experiment

Description: A series of in-pile experiments has been conducted at Sandia Laboratories to provide information on pressure levels and conversion of thermal energy into mechanical work in LMFBR cores during hypothetical, superprompt-critical excursions. Pressures generated in these experiments are recorded by a pressure transducer located at the top and bottom of a sodium channel surrounding a single, fresh UO/sub 2/ fuel pin. Work energy conversion is measured by a linear motion transducer connected to a pis… more
Date: January 1, 1977
Creator: Young, M. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Prompt burst energetics experiments: fresh oxide/sodium series

Description: A series of in-pile experiments has been performed to provide information on thermal energy to work conversion under prompt burst excursion (PBE) conditions. These consisted of single pin tests using fresh uranium oxide or uranium carbide fuel in a capsule geometry, with either stagnant sodium or helium in the coolant channel. The experiments were irradiated with single or double pulses in the Annular Core Pulse Reactor (ACPR) to provide energy depositions up to 2900 J/g. This report covers the… more
Date: August 1, 1978
Creator: Reil, K.O. & Young, M.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental Breeder Reactor-II dynamic modeling and code verification

Description: The Experimental Breeder Reactor No. 2 (EBR-II) has been modeled using a recently developed special purpose block oriented simulation language, the Dynamic Simulator for Nuclear Power Plants (DSNP). The purpose of the work was to develop and verify the code and use it to support the Operational Reliability Test Program at EBR-II. Designed to be set up directly from block diagrams of the reactor system, DSNP allows easy interchange of modules which simulate individual components of the plant wit… more
Date: June 1, 1983
Creator: Lehto, W. K.; Dean, E. M.; Larson, H. A. & Koenig, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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