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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
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 breeder program are EBR-II, FFTF and TREAT. For the fusion program, RTNS-II and FMIT were selected.
Date: January 1, 1982
Creator: Evans, E.A.; Cox, C.M. & Jackson, R.J.
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.
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 requirements, describes the design and special features, presents test procedures ad relates significant operating experience.
Date: April 16, 1984
Creator: Crandall, D.L.
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 experience. Available courses are described.
Date: January 1, 1984
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.
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 for ex-core detectors were found to be particularly insensitive to the calculational method. This apparently resulted from two facts: (1) the calculated factors are ratios of ratios, which reduce the sensitivity to first order corrections, and (2) most neutrons which cause reactions in an ex-core detector originate in the small volume of core nearest to the detector. Maps of key parameters in the MSM technique have been generated to promote a general understanding of the method and to assure its proper application.
Date: January 1, 1978
Creator: Carpenter, S. G.; McFarlane, H. F.; Lineberry, M. J. & Beck, C. L.
Partner: UNT Libraries Government Documents Department
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Studies of spatial decoupling in heterogeneous LMFBR critical assemblies

Description: Recent measurements at the Zero Power Plutonium Reactor have studied the spatial decoupling in large, heterogeneous assemblies. These assemblies exhibited a significantly greater degree of decoupling than previous homogeneous assemblies of similar size. The flux distributions in these heterogeneous assemblies were very sensitive reactivity perturbations, and perturbed flux distributions were achieved relatively slowly. Decoupling was investigated using rod-drop, boron-oscillator and noise-coherence techniques which emphasized different times following the perturbations. Reactivity changes could be measured by analyzing the power history from a single detector using inverse kinetics methods with the assumption of an instantaneous efficiency change for the detector. For assemblies more decoupled than ZPPR-13, the instantaneous efficiency change assumption begins to be invalid.
Date: January 1, 1984
Creator: Brumbach, S.B.; Goin, R.W. & Carpenter, S.G.
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
Partner: UNT Libraries Government Documents Department
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Irradiation facilities at Oak Ridge National Laboratory

Description: Several irradiation facilities at two of Oak Ridge National Laboratory's nuclear reactors (HFIR, ORR) are described. The range of facilities available will accommodate specimen sample sizes from a few millimeters in diameter up to 600 mm square. Nuclear characteristics of these facilities range to a maximum of 1.2 x 10/sup 19/ n/m/sup 2/s fast neutron flux; 2.9 x 10/sup 19/ n/m/sup 2/s thermal neutron flux; and 1.8 x 10/sup 10/ R/h gamma flux.
Date: January 1, 1984
Creator: Thoms, K.R.; Conlin, J.A. & West, C.D.
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor technical specifications

Description: Included are sections covering safety limits and limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls. An appendix deals with accidents and anticipated transients. (DG)
Date: March 1, 1977
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 to simulate key events in the loss-of-flow accident scenario for the Clinch River homogeneous reactor.
Date: January 1, 1985
Creator: Morris, E. E.; Simms, R. & Gruber, E. E.
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 external and internal exposure control, respiratory protection procedures, radiation surveillance practices, radioactive waste management, and engineering controls for confining radiation contamination. The theory, design, and operating experience at LMFBRs is described. Aspects of LMFBR health physics different from the LWR experience in the United States are identified. Suggestions are made for modifications to the NRC Standard Review Plan based on the differences.
Date: October 1, 1985
Creator: Adams, S. R.
Partner: UNT Libraries Government Documents Department
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Clinch River Breeder Reactor Plant Project: construction schedule

Description: The construction schedule for the Clinch River Breeder Reactor Plant and its evolution are described. The initial schedule basis, changes necessitated by the evaluation of the overall plant design, and constructability improvements that have been effected to assure adherence to the schedule are presented. The schedule structure and hierarchy are discussed, as are tools used to define, develop, and evaluate the schedule.
Date: January 1, 1982
Creator: Purcell, W.J.; Martin, E.M. & Shivley, J.M.
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 resolution. Second, could collimator and shield structures be fabricated for the Annular Core Pulsed Reactor (ACPR), for which the system is being built, that would provide acceptable signal to background ratios. Both of these questions can now be answered in the affirmative because of the favorable experiments recently conducted at the Sandia Pulsed Reactor (SPR II) and at the ACPR.
Date: January 1, 1977
Creator: Kelly, J. G. & Stalker, K. T.
Partner: UNT Libraries Government Documents Department
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Analysis of gas-cooled fast reactor shield designs

Description: In its shielding program for the Gas-Cooled Fast Reactor (GCFR) as conceived by General Atomic, Oak Ridge National Laboratory has developed an advanced shielding analysis system that incorporates the latest analysis techniques for converging to a shield design compatible with other design parameters such as cooling and structural requirements or material compatibility. Basically the system consists in applying the various techniques in a logical sequence to a given design, thereby generating a large body of data to serve as an information base for subsequent redesign. As an illustration, this system is applied to successive typical models for the GCFR, resulting in a reduction in the thickness of the radial shield and redesign of the lower shield region. In principle, the design-analysis-redesign iterations would continue until they converge upon an acceptable configuration.
Date: January 1, 1978
Creator: Bartine, D. E. & Williams, L. R.
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 fuel cycle requirements.
Date: January 1, 1980
Creator: Rainey, R.H.; Burch, W.D.; Haire, M.J. & Unger, W.E.
Partner: UNT Libraries Government Documents Department
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Developments in the LASL Fuel Pin Imaging System: PINEX-3A

Description: The LASL Fuel Pin Imaging System was evaluated using a series of 10 TREAT transients, each of approx. 240-MW peak power. HEDL provided the fuel-ejection type capsule with annular fuel pellets. The pin visibility threshold was determined to be approx. 20-MW of TREAT power (approx. 130 W/g), almost an order of magnitude improvement over our PINEX-2 threshold. The impact of changes in instrumentation, imaging apertures, and fluors that produced the improved sensitivity are reported. Results of a time-integrated imaging technique are also presented.
Date: January 1, 1979
Creator: Lumpkin, A. H.; Berzins, G. J.; Cosimi, R. A.; O'Hare, T. E. & Davidson, J. R.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fast Breeder Reactors: a bibliography

Description: This bibliogralphy includes 5465 selected citations on LMFBR development. The citations were compiled from the DOE Energy Data Base covering the period January 1978 (EDB File No. 78R1087) through August 1980 (EDB File No. 80C79142). The references are to reports from the Department of Energy and its contractors, reports from other government or private organizations, and journal articles, books, conference papers, and monographs from US originators. Report citations are arranged alphanumerically by report number; nonreport literature citations are arranged chronologically. Corporate, Personal Author, Subject, and Report Number Indexes are provided in Volume 2.
Date: November 1, 1980
Creator: Raleigh, H.D. (ed.)
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fast Breeder Reactors: a bibliography

Description: This bibliography includes 5465 selected citations on LMFBR development. The citations were compiled from the DOE Energy Data Base covering the period January 1978 (EDB File No. 78R1087) through August 1980 (EDB File No. 80C79142). The references are to reports from the Department of Energy and its contractors, reports from other government or private organizations, and journal articles, books, conference papers, and monographs from US originators. Report citations are arranged alphanumerically by report number; nonreport literature citations are arranged chronologically. Corporate, Personal Author, Subject, and Report Number Indexes are provided in Volume 2.
Date: November 1, 1980
Creator: Raleigh, H.D. (ed.)
Partner: UNT Libraries Government Documents Department
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Cover gas seals. 11 - FFTF-LMFBR seal-test program, January-March 1974

Description: The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment, (2) demonstrate that these FFTF seals or new seal configuration provide acceptable fission product and cover gas retention capabilities at LMFBR Clinch River Plant operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the LMFBR Clinch River Plant to support the national objective to reduce all atmospheric contaminations to low levels.
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R. & Welch, F.
Partner: UNT Libraries Government Documents Department
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