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Criticality experiments with mixed oxide fuel pin arrays in plutonium-uranium nitrate solution

Description: A series of critical experiments was completed with mixed plutonium-uranium solutions having a Pu/(Pu + U) ratio of approximately 0.22 in a boiler tube-type lattice assembly. These experiments were conducted as part of the Criticality Data Development Program between the United States Department of Energy (USDOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of the experiments and data are included in this report. The experiments were perf… more
Date: August 1, 1988
Creator: Lloyd, R.C. (Pacific Northwest Lab., Richland, WA (United States)) & Smolen, G.R. (Oak Ridge National Lab., TN (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validation of SSC using the FFTF natural-circulation tests

Description: As part of the Super System Code (SSC) validation program, the 100% power FFTF natural circulation test has been simulated using SSC. A detailed 19 channel, 2 loop model was used in SSC. Comparisons showed SSC calculations to be in good agreement with the Fast Flux Test Facility (FFTF), test data. Simulation of the test was obtained in real time.
Date: January 1, 1982
Creator: Horak, W.C.; Guppy, J.G. & Kennett, R.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility. Design and Development Quality Assurance Requirements for the FFTF

Description: The document is presented to provide general management requirements for Pacific Northwest Laboratory (PNL) and contractor design and development quality assurance programs to assure the required quality level of the various items required for the FFTF. The document is applicable as imposed by the contract to FFTF contractors and subcontractors. The document is also applicable to PNL design and development activities related to the FFTF.
Date: October 23, 1968
Creator: Albert, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of the core support and restraint structures for FFTF and CRBRP

Description: This paper presents and compares the design and fabrication of the FFTF and CRBRP reactor structures which support and restrain the reactor core assemblies. The fabrication of the core support structure (CSS) for the FFTF reactor was completed October 1972 and this paper discusses how the fabrication problems encountered with the FFTF were avoided in the subsequent design of the CRBR CSS. The radial core restraint structure of the FFTF was designed and fabricated such that an active system coul… more
Date: December 1, 1977
Creator: Sutton, H.G. & Rylatt, J.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Rod scanner assay of FFTF fuel

Description: Rod scanner results for over 40,000 FFTF Cores 1 and 2 fuel pins are summarized. An improved rod scanner calibration technique for FFTF Cores 3 and 4 fuel pins is described. Data are compared with chemical assay measurements. 5 fig., 5 tables.
Date: January 1, 1978
Creator: Goris, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cycle 7 outage experience. [Fast Flux Test Facility (FFTF)]

Description: The scheduled 58-day refueling outage in preparation for the seventh operating cycle of the Fast Flux Test Facility (FFTF) was successfully completed three days ahead of schedule. The planning and execution of the outage was greatly aided by Project/2 automated scheduling capabilities. For example, the use of ''maintenance windows'' and resource loading capabilities was particularly effective. The value of the planning process was demonstrated by the smooth transition into the outage phase afte… more
Date: March 1, 1986
Creator: Gadeken, A.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Acoustic Emission Weld Monitoring of Nuclear Components

Description: Acoustic emission monitoring augments other nondestructive testing methods and is sometimes applicable when other tests cannot be applied. This is, in part, due to the high sensitivity of acoustic emission monitoring. Acoustic emission monitoring is only sensitive to active flaw-growth, however, and will not detect a flaw in equilibrium. This paper describes the application of acoustic emission monitoring to nuclear reactor fuel pin end closure welds and other weldments of the reactor piping.
Date: January 25, 1972
Creator: Romrell, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Packaging and shipment of U. S. breeder reactor experiments

Description: Irradiation testing of fuels and materials in the Fast Test Reactor (FTR) required development of a shipping cask (designated T-3) and associated hardware for loading and shipping of these experiments to postirradiation examination facilities. The T-3 shipping-cask program included design, fabrication, and testing of internal cask packages to protect the experiments during loading, shipping, and unloading. The cask was designed for loading in both the vertical and horizontal attitudes.
Date: January 1, 1980
Creator: Berger, J. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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FFTF utilization for irradiation testing

Description: FFTF utilization for irradiation testing is beginning. Two Fuels Open Test Assemblies and one Vibration Open Test Assembly, both containing in-core contact instrumentation, are installed in the reactor. These assemblies will be used to confirm plant design performance predictions. Some 100 additional experiments are currently planned to follow these three. This will result in an average core loading of about 50 test assemblies throughout the early FFTF operating cycles.
Date: January 1, 1980
Creator: Corrigan, D. C.; Julyk, L. J.; Hoth, C. W.; McGuire, J. C. & Sloan, W. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility loose-parts monitor

Description: This paper summarizes the development testing in progress at the FFTF to determine the effectiveness of high temperature microphones as acoustic monitors in the upper plenum of the FFTF. The specific goal of this testing is development of an automated loose parts monitor for the upper plenum. A description of the acoustic probe is included, as well as a discussion of the signal processing. A summary of the results to date is also given.
Date: February 1, 1982
Creator: Sloan, W.R.; King, D.C. & Robles, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Permeability and solubility of gases for FFTF/CRBRP cover-gas-seal materials

Description: The permeability (anti P) and diffusion coefficient (D) of the gases H/sub 2/, Ar, Kr and Xe have been measured in certain elastomer materials of interest to the FFTF/CRBRP Cover Seal Program. These elastomers include Buna N, Buna S, Butyl Rubber, ethylene-propylene polyacrylic, polyurethane and silicone. Measurements were made over the temperature range 100 to 300/sup 0/F. Data for the permeability and diffusion coefficient for these gases in the above elastomer materials are given. The method… more
Date: January 1, 1974
Creator: Darnell, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cover-gas seals. FFTF-LMFBR seal-test program. Progress report, January-March 1975

Description: The objectives of the general seal test 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 configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmenta… more
Date: January 1, 1975
Creator: Horton, P.; Oliva, R. & Shimazki, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and operation of a passive neutron monitor for assaying the TRU content of solid wastes

Description: A passive neutron monitor has been designed and built for determining the residual transuranic (TRU) and plutonium content of chopped leached fuel hulls and other solid wastes from spent Fast Flux Test Facility (FFTF) fuel. The system was designed to measure as little as 8 g of plutonium or 88 mg of TRU in a waste package as large as a 208-l drum which could be emitting up to 220,000 R/hr of gamma radiation. For practical purposes, maximum assay times were chosen to be 10,000 sec. The monitor c… more
Date: February 1, 1984
Creator: Brodzinski, R.L.; Brown, D.P.; Rieck, H.G. Jr. & Rogers, L.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of process inventory uncertainties

Description: This paper discusses the determination of some of the process inventory uncertainties in the Fast Flux Test Facility (FFTF) process line at the Los Alamos Scientific Laboratory (LASL) Plutonium Processing Facility (TA-55). A brief description of the FFTF process is given, along with a more detailed look at the peroxide precipitation and re-dissolution (PR) process. Emphasis is placed on the identification of the product and sidestreams from the unit processes, as they have application to the ac… more
Date: January 1, 1980
Creator: Roberts, N.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reactivity analysis of core distortion effects in the FFTF

Description: An improved technique for evaluating core distortion reactivity effects was developed using reactivity analyses of two core geometry models (R-Z and HEX). This technique is incorporated into a new processor code called CORDIS. The advantages of this technique over existing reactivity models are that is preserves core heterogeneity, provides a control rod insertion effect model, uses row-dependent axial shape functions, and provides a flexible and cost efficient core distortion reactivity analys… more
Date: January 1, 1982
Creator: Knutson, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium-fire control by space isolation with nitrogen flooding: FFTF proof test F2

Description: Sodium fire protection by space isolation with nitrogen flooding was evaluated by performing a large-scale sodium fire test within a mockup of an FFTF secondary sodium system pipeway. The full scale (3350 ft/sup 3/) mockup was initially filled with air and its leak tightness set to correspond to that expected in an actual FFTF pipeway. The basis for specifying the rate of nitrogen flood gas is discussed ad the experimental verification provided. Nitrogen flooding was activated 15 minutes after … more
Date: June 1, 1974
Creator: Hilliard, R.K. & Muhlestein, L.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cover gas seals: FFTF-LMFBR seal test program

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 configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions other … more
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R.; Welch, T.S. & Shimazaki, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Initial physics measurements on FFTF

Description: Initial criticality of the Fast Flux Test Facility (FFTF) was achieved on February 9, 1980 at 3:45 p.m. During the period November 27, 1979 to March 8, 1980, fuel was loaded into the FFTF core, initial criticality was achieved, and several subcritical physics measurements were performed. The data obtained from initial FFTF nuclear operation are presented. Specifically, the absolute and relative neutron count rates were predicted for the bulk of the seventy-three fuel loadings of FFTF. Agreement… more
Date: January 1, 1980
Creator: Bennett, R. A.; Daughtry, J. W.; Harris, R. A.; Jones, D. H.; King, T. L.; Midgett, J. C. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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FFTF startup: status and results

Description: Startup testing on the Fast Flux Test Facility (FFTF) during the past three years has progressed beyond initial criticality toward the principal goal of power demonstration in 1980. An overview is presented of technical results to date and project plans to achieve power demonstration and complete the startup test program.
Date: March 1, 1980
Creator: Noordhoff, B. H. & Moore, C. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SAS3D analysis of natural convection boiling behavior in the Sodium Boiling Test Facility

Description: The objective of the initial phase of testing in the Sodium Boiling Test (SBT) Facility, at the Oak Ridge National Laboratory, was to determine the maximum power that could be transferred by a simulated breeder reactor coolant subchannel when the coolant flow is driven by natural convection. In order to aid in the evaluation of the experimental data and to help understand the flow regimes present at the various power levels examined during this test program, a SAS3D computer model of the SBT Fa… more
Date: January 1, 1979
Creator: Klein, G. & Dunn, F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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