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Evaluation of materials for retention of sodium and core debris in reactor systems. Annual progress report, September 1977-December 1978. [LMFBR]

Description: This report considers some of the consequences of a hypothetical core disruptive accident in a nuclear reactor. The interactions expected between molten core debris, liquid sodium, and materials that might be employed in an ex-vessel sacrificial-bed or in the reactor building are discussed. Experimental work performed for NRC by Sandia Laboratories and Hanford Engineering Development Laboratory on the interactions between liquid sodium and basalt concrete is reviewed. Studies of molten steel interactions with concrete at Sandia Laboratories and molten UO/sub 2/ interactions with concrete at The Aerospace Corporation are also discussed. The potential of MgO for use in core containment is discussed and refractory materials other than MgO are reviewed. Finally, results from earlier experiments with molten core debris and various materials performed at The Aerospace Corporation are presented.
Date: December 1, 1978
Creator: Swanson, D.G.; Zehms, E.H.; McClelland, J.D.; Meyer, R.A. & van Paassen, H.L.L.
Partner: UNT Libraries Government Documents Department

Evaluation of the feasibility, economic impact, and effectiveness of underground nuclear power plants. Final technical report

Description: Information on underground nuclear power plants is presented concerning underground nuclear power plant concepts; public health impacts; technical feasibility of underground concepts; economic impacts of underground construction; and evaluation of related issues.
Date: May 1, 1978
Partner: UNT Libraries Government Documents Department

Thermal insulation system design and fabrication specification (nuclear) for the Clinch River Breeder Reactor plant

Description: This specification defines the design, analysis, fabrication, testing, shipping, and quality requirements of the Insulation System for the Clinch River Breeder Reactor Plant (CRBRP), near Oak Ridge, Tennessee. The Insulation System includes all supports, convection barriers, jacketing, insulation, penetrations, fasteners, or other insulation support material or devices required to insulate the piping and equipment cryogenic and other special applications excluded. Site storage, handling and installation of the Insulation System are under the cognizance of the Purchaser.
Date: July 21, 1978
Partner: UNT Libraries Government Documents Department

Process heat reactor design and analaysis. Quarterly progress report, April 1-June 30, 1978

Description: This report summarizes the third quarter FY-1978 results of concept design studies at General Atomic Company (GA) for an 842-MW(t) VHTR utilizing an intermediate helium heat transfer loop to provide thermal energy for the production of reducing gas (H/sub 2/ + CO) by steam-reforming a light hydrocarbon. Basic carbon sources may be coal, residual, or oil shale. The report summarizes the various plant configurations selected for the study and presents the conceptual plant layout drawings. Results of design studies on the intermediate heat exchanger are also presented. The status of the performance/optimization code development is discussed, and completion of the core auxiliary cooling system study is summarized.
Date: June 30, 1978
Partner: UNT Libraries Government Documents Department

Demonstration of fuel resistant to pellet-cladding interaction. First semiannual report, July-December 1977

Description: Objective is the demonstration od advanced fuel concepts that are resistant to the failure mechanism known as fuel pellet-cladding interaction (PCI). Since currently used fuel in the nuclear power industry is subject to the PCI failure mechanism, reactor operators limit the rates of power increases and thus reduce their capacity factors in order to protect the fuel. Two barrier concepts are being prepared for demonstration: (a) Cu-Barrier fuel and (b) Zr-Liner fuel. The large-scale demonstration of the PCI-resistant fuel is being designed generically to show feasibility of such a demonstration in a commercial power reactor of type BWR/3 having a steady-state core. Using the core of Quad Cities-1 reactor at the beginning of Cycle 6, the insertion of the demonstration PCI-resistant fuel and the reactor operational plan are being designed. Support laboratory tests to date for the Demonstration have shown that these barrier fuels (both the Cu-Barrier and the Zr-Liner types) are resistant to PCI. Four lead test assemblies (LTA) of the advanced PCI-resistant fuel are being fabricated for insertion into the Quad Cities-1 Boiling Water Reactor at the beginning of Cycle 5 (January 1979).
Date: February 1, 1978
Creator: Rosenbaum, H.S. (comp.)
Partner: UNT Libraries Government Documents Department

Advanced gas cooled nuclear reactor materials evaluation and development program. Selection of candidate alloys. Vol. 1. Advanced gas cooled reactor systems definition

Description: Candidate alloys for a Very High Temperature Reactor (VHTR) Nuclear Process Heal (NPH) and Direct Cycle Helium Turbine (DCHT) applications in terms of the effect of the primary coolant exposure and thermal exposure were evaluated. (FS)
Date: October 31, 1978
Creator: Marvin, M.D.
Partner: UNT Libraries Government Documents Department

Dresden Unit Two: dilute chemical decontamination and alternate water chemistry. Progress report, July 1-31, 1978

Description: Most of the Dilute Chemical Decontamination Program effort was expended on the VNC test loop simulation of a BWR decontamination. The various tasks in the Alternate Water Chemistry Program are reported on: dose rate, offgas system, leakage monitoring, materials, condensate treatment, additives, etc. (DLC)
Date: September 21, 1978
Creator: Blomgren, J. C.
Partner: UNT Libraries Government Documents Department

Leakage and motion detection system for the flexible-joint assembly, large-scale LMFBR

Description: Flexible joint assemblies in the primary sodium piping to the large scale LMFBR pressure vessel are designed to accommodate thermal expansion of the piping system. To monitor the performance of the flexible joint assemblies during reactor operation, sodium leakage and flexible joint motion detection/sensors are specified. This report describes the mechanical/hydraulic portions only of the leak detection and motion monitoring system. A tentative choice of displacement transducer and its readout equipment is presented. However, the required EI and C portion of the monitoring system is not covered.
Date: August 1, 1978
Creator: Gaspar, N.L.
Partner: UNT Libraries Government Documents Department

High Flux Isotope Reactor. Quarterly report, October--December 1977

Description: Routine reactor operation with four end-of-cycle shutdowns and one scheduled cycle interruption shutdown resulted in an on-stream time of 90.3 percent. A new inner control cylinder and a set of outer control plates with remotely replaced bearing brackets were installed. The semiannual core component inspection was made.
Date: March 1, 1978
Creator: Corbett, B. L.; McCord, R. V. & Poteet, K. H.
Partner: UNT Libraries Government Documents Department

26 - LMFBR flexible pipe joint development

Description: Objective is the qualification of a PLBR-size primary loop flexible piping joint to the ASME Band PVC rules. Progress and activities are reported for: Class 1 flexible joint code approval support, engineering and design, material development, component testing, and manufacturing development. (DLC)
Date: May 1, 1978
Creator: Anderson, R.V.
Partner: UNT Libraries Government Documents Department

Evaporative removal of sodium: interim progress report and preliminary facility specification

Description: A summary of the current Evaporative Removal of Sodium (ERNA) activities at the Energy Systems Group is presented. Also included is a review of earlier work on sodium evaporation. As a result of this work it was concluded that the ERNA process was extremely successful and worthy of future consideration as a recognized process for reactor components. Also included in the report is a Preliminary Outline Specification for a large facility to remove sodium from full size CRBR fuel rod assemblies.
Date: September 27, 1978
Creator: Welch, F.H.
Partner: UNT Libraries Government Documents Department

Hydrodynamic design report intermediate size inducer pump for sodium operation

Description: An inducer pump has been designed to fit within the existing housing of the FFTF Facility. The design has been shown to meet the specified requirements in every area where an analytical prediction of the performance can be made. The head-rise and efficiency of the pump have design margins so that the calculated values actually exceed requirements over the full range of operation. The suction performance of the design provides a very large margin at the operating NPSH value which is the major advantage of using the inducer pump. The suction performance margin at off-design is estimated to be adequate for suction performance, but may not be as large as desired for life considerations. The design has incorporated features that provide for long life at the design point. These features have been established based on proven performance of commercial waterjet pumps designed by Rocketdyne.
Date: April 26, 1978
Creator: King, J.A.; O'Hern, F.C. & Jackson, E.D.
Partner: UNT Libraries Government Documents Department

Gas reactor international cooperative program interim report. HTR Multiplex market assessment

Description: The HTR Multiplex utilizes the HTR as an energy source to produce multiple forms of energy. A specific type of multiplex utilizing a high temperature chemical heat pipe (CHP) is examined. Forecasts of the US electric energy markets and industrial heat markets are developed for the 1995-2010 time period. Costs of multiplexes in these markets are compared to costs of the conventional forecast mix of electric generation systems and to costs of fluidized bed combustors in the industrial heat market. The comparisons are by National Electric Reliability Council (NERC) region. The major finding of the study is that a large potential US market exists for the HTR Multiplex in two segments of the electric and industrial heat markets. It is concluded that the HTR Multiplex can provide peaking and mid-range electricity plus industrial heat for one and two-shift operations at costs approximately 50 percent lower than available alternatives. This market is estimated to be at least 300 GW/sub t/ (about 7 quads per year) in the 1995 to 2010 time period.
Date: September 1, 1978
Creator: Leeth, G.G. & Meyer, C.F.
Partner: UNT Libraries Government Documents Department

Cover gas seals: 26-cover gas seal components

Description: Progress during the report period included CRBRP inflatable seal vendor qualification (Presray Inc.), static inflatable seal development, high-temperature seal degradation, and alternate seal concepts (supported and cantilevered rings). (DLC)
Date: January 1, 1978
Creator: Steele, O.P. III & Horton, P.H.
Partner: UNT Libraries Government Documents Department

Commercial LMFBR steam generator design comparison. Final report for period from 1 October 1977 through 30 September 1978

Description: This report presents results obtained from the commercial LMFBR Steam Generator Design Comparison Study from 1 October 1977 through 30 September 1978 relative to selecting the preferred steam generator design for a commercial-size plant using a Benson, Sulzer, or saturated steam cycle. The primary emphasis was placed on identifying potential problem areas in each design for each steam cycle. The study indicates the hockey stick design as the preferred concept for each steam cycle.
Date: September 30, 1978
Creator: Newburn, F.
Partner: UNT Libraries Government Documents Department

Fuel performance improvement program. Quarterly progress report October--December 1978. [BWR; PWR]

Description: The Fuel Performance Improvement Program has as its objective the identification and demonstration of fuel concepts with improved power ramp performance. Improved fuels are being sought to allow reduction or elimination of fuel related operating guidelines on nuclear power plants such that the fuel may be power manuvered within the rates allowed by the system technical specifications. The program contains a combination of out-of-reactor studies, in-reactor experiments and in-reactor demonstrations. Fuel concepts initially being considered include annular pellets, cladding internally coated with graphite and packed-particle fuls. The performance capability of each concept will be compared to a reference fuel of contemporary pellet design by irradiations in the Halden Boiling Water Reactor. Fuel design and process development is being completed and fuel rod fabrication will begin for the Halden test rods and for the first series of in-reactor experiments. The in-reactor demonstrations are being performed in the Big Rock Point reactor to show that the concepts pose no undue risk to commercial operation. Additional concepts may be considered as the result of a state-of-the-technology review of fuel-cladding interaction and assessment of fuel concepts and the out-of-reactor studies. The results of the program will be used to establish the technical bases for design of fuels with improved power ramp performance.
Date: January 1, 1978
Creator: Crouthamel, C.E. (comp.)
Partner: UNT Libraries Government Documents Department

Fabrication details for wire wrapped fuel assembly components. [LMFBR]

Description: Extensive hydraulic testing of simulated LMFBR blanket and fuel assemblies is being carried out under this MIT program. The fabrication of these test assemblies has involved development of manufacturing procedures involving the wire wrapped pins and the flow housing. The procedures are described in detail in the report.
Date: September 1, 1978
Creator: Bosy, B.J.
Partner: UNT Libraries Government Documents Department

Interim report on cold trap alternatives, sodium technology

Description: This is an interim report on the modifications which are being made to an existing sodium loop so that a new method of removing hydrogen from sodium can be evaluated in a flowing sodium system. Some preliminary results on the performance of this type of cold trap alternative in a static sodium system are reported. Some tentative reactor design parameters for this type of getter device are presented based on the static test results. The life of such a unit is calculated to be substantially greater than that of a cold trap of equal volume.
Date: September 18, 1978
Creator: Hill, E.F.
Partner: UNT Libraries Government Documents Department

Steam generator tube denting simulation testing. [PWR]

Description: Tube denting has been reported in steam generators in a number of commercial nuclear power plants in recent years. In order to aid in understanding of the mechanism leading to tube denting in the steam generators, a Bettis laboratory test program was initiated to attempt to reproduce tube denting and to investigate the effects of chemistry, design, and temperature. The results of the tests indicate that denting can be reproduced in the small model steam generator test apparatus devised for this testing. Denting was observed under carbon steel support plates in seawater-contaminated secondary water in a test with hydrazine-ammonia chemistry and a primary water inlet temperature of 590/sup 0/F and in a test with hydrazine-morpholine chemistry and a primary water inlet temperature of 545/sup 0/F. The parameters of these two tests simulate conditions in a typical commercial steam generator and the Shippingport Atomic Power Station steam generators, respectively.
Date: February 1, 1978
Creator: Battaglia, P.J. & Singley, W.J.
Partner: UNT Libraries Government Documents Department

Simple representations of spectrum averaged cross sections in LMFBR blankets

Description: The setting up of correlations to represent spectrum averaged cross sections in the core-blanket interface and blanket region of LMFBRs is described. Analytical representations of concentrations as functions of position are used. Sample calculations using a CRBR core composition are presented.
Date: January 1, 1978
Creator: Badruzzaman, A.; Wiley, R. & Becker, M.
Partner: UNT Libraries Government Documents Department

Turbulent sweeping flow mixing model for wire wrapped LMFBR assemblies

Description: A physical model is proposed to derive the sweeping flow for LMFBR triangular array wire-wrapped assemblies under the turbulent flow condition. Two correlations are suggested for the sweeping flow through two different types of gaps between subchannels, the gap between the interior subchannels and the gap between the wall subchannels. These two sweeping flow correlations are evolved by calibrating the constants in the proposed model against the available experimental data. Agreement between the correlations and all the experimental data of +- 35% is obtained over the assembly design range of 1.315 > P/D > 1.067 and 52 > H/D > 4. Based on these correlations, flow sweeping input parameters for two popular computer codes, i.e., COBRA and SUPERENERGY, are recommended.
Date: October 1, 1978
Creator: Chiu, C.; Rohsenow, W.M. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department

Large-systems improvement studies

Description: A set of five backup decay heat removal candidate schemes has been studied in sufficient depth to create conceptual arrangements, P and I diagrams, and equipment lists for each. A summary of the attributes of each system arrangement is developed. System costs were also developed but do not show significant differences.
Date: September 1, 1978
Creator: Riedel, R.H.
Partner: UNT Libraries Government Documents Department