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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

Producing a unified progress report with inputs from several contractors

Description: The project management organization in which the author works produces an annual technical progress report for the Clinch River Breeder Reactor Plant Project. The report has to be integrated and edited from the inputs of six major Project participants scattered from coast to coast. The integrated report manuscript then has to be submitted for two formal reviews, and the report must be published in a readable and attractive form. Accomplishing those steps in a reasonable length of time, with a high degree of accuracy, and at minimum expense requires careful planning and close supervision. Planning includes scheduling in such a way as to perform operations in parallel, where possible, instead of in series. Exploiting the capabilities of word processing saves much keyboarding and proofreading time. Art from previous reports is reused when possible. Many of these methods can be applied to other reports that require integration and editing of material from several sources.
Date: January 1, 1981
Creator: Nelson, O.A.
Partner: UNT Libraries Government Documents Department

Clinch River Breeder Reactor Plant project. Summary edition, 1981 technical progress report, October 1980-September 1981

Description: This report describes the objectives, design decisions, and major accomplishments achieved in planning, organizing, designing, and managing the CRBRP Project during this period. It includes inputs from the CRBRP Architect-Engineer (Burns and Roe, Inc.), from the Constructor (Stone and Webster Engineering Corporation), and from the supporting Reactor Manufacturers (Atomics International Division of the Energy Systems Group of Rockwell International Corporation, the Advanced Reactor Systems Department of General Electric Company, and the Advanced Reactors Division of Westinghouse Electric Corporation).
Date: January 1, 1981
Partner: UNT Libraries Government Documents Department

Effect of nonuniform inlet air flow on air-cooled heat-exchanger performance

Description: Blowers used to propel air across tube bundles generate a non-uniform flow field due to their construction details. A formalism to evaluate heat transfer degradation due to non-uniform airflow has been developed. Certain symmetry relations for cross flowheat exchangers, heretofore unavailable in the open literature, have been derived. The solution presented here was developed to model a 4 tube pass air blast heat exchanger for the Clinch River Breeder Reactor Plant Project. This case is utilized to show how this method can be used as a design tool to select the most suitable blower construction for a particular application. A numerical example is used to illustrate the salient points of the solution.
Date: January 1, 1983
Creator: Soler, A.I.; Singh, K.P. & Ng, T.L.
Partner: UNT Libraries Government Documents Department

Irradiation behavior of metallic fast reactor fuels

Description: Metallic fuels were the first fuels chosen for liquid metal cooled fast reactors (LMR's). In the late 1960's world-wide interest turned toward ceramic LMR fuels before the full potential of metallic fuel was realized. However, during the 1970's the performance limitations of metallic fuel were resolved in order to achieve a high plant factor at the Argonne National Laboratory's Experimental Breeder Reactor II. The 1980's spawned renewed interest in metallic fuel when the Integral Fast Reactor (IFR) concept emerged at Argonne National Laboratory. A fuel performance demonstration program was put into place to obtain the data needed for the eventual licensing of metallic fuel. This paper will summarize the results of the irradiation program carried out since 1985.
Date: January 1, 1991
Creator: Pahl, R.G.; Porter, D.L.; Crawford, D.C. & Walters, L.C.
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

Analysis of the lumped fission-product uncertainty in CRBR

Description: An approximation made in most fast reactor analyses is to utilize a single lumped fission product (FP) cross-section set to represent the total effect of the approximately 800 possible fission product nuclides in a depleted reactor model. Recent investigations have analyzed several aspects of this one-lump approximation (burnup dependence, comparison with a two-lump model, etc.), but little has been done in addressing the quality, or uncertainty, in the basic cross-section data utilized in any such representation. Thus, the purpose of this study is to investigate the uncertainty in the FP reactivity effect due to the data uncertainties inherent in an ENDF/B-V composite FP representation specifically designed for application with the current CRBR heterogeneous core concept.
Date: January 1, 1981
Creator: White, J.R. & Schenter, R.E.
Partner: UNT Libraries Government Documents Department

Human factors engineering in Clinch River Breeder plant design

Description: The Clinch River Breeder Reactor Plant (CRBRP) Project formed a Control Room Task Force to ensure that lessons learned from the Three Mile Island accident are incorporated into the design. The charter for the Control Room Task Force was to review plant operations from the control room. The focus was on the man-machine interface to ensure that the systems' designs and operator actions meshed to properly support plant operation during normal and off-normal conditions. Specific items included for review are described. This paper describes the methodology utilized to accomplish the Task Forces' objectives and the results of the review.
Date: January 1, 1982
Creator: Planchon, H.P. Jr.; Kaushal, N.N. & Snider, J.
Partner: UNT Libraries Government Documents Department

Impacts of data covariances on the calculated breeding ratio for CRBRP

Description: In order to establish confidence on the data adjustment methodology as applied to LMFBR design, and to estimate the importance of data correlations in that respect, an investigation was initiated on the impacts of data covariances on the calculated reactor performance parameters. This paper summarizes the results and findings of such an effort specifically related to the calculation of breeding ratio for CRBRP as an illustration. Thirty-nine integral parameters and their covariances, including k/sub eff/ and various capture and fission reaction rate ratios, from the ZEBRA-8 series and four ZPR physics benchmark assemblies were used in the least-squares fitting processes. Multigroup differential data and the sensitivity coefficients of those 39 integral parameters were generated by standard 2-D diffusion theory neutronic calculational modules at ANL. Three differential data covariance libraries, all based on ENDF/B-V evaluations, were tested in this study.
Date: January 1, 1983
Creator: Liaw, J.R.; Collins, P.J.; Henryson, H. II & Shenter, R.E.
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

Final design analyses of CRBRP fuel rod

Description: The key results are presented of the CRBRP fuel rod analyses performed in support of the CRBRP fuel assembly final design review in December, 1977. For the CRBRP fuel rod design environment, it is shown that the life limiting criteria on ductility limited strain (DLS) and cumulative damage function (CDF) are satisfied. The conservatism in these analyses is demonstrated by comparison to the upset enthalpy based failure potential criteria derived from cladding breach experience for TREAT simulated unterminated rapid reactivity insertion transients.
Date: January 1, 1980
Creator: Bishop, B.A. & Vijuk, R.M.
Partner: UNT Libraries Government Documents Department

Alignment and operability analysis of a vertical sodium pump

Description: With the objective of identifying important alignment features of pumps such as FFTF, HALLAM, EBR II, PNC, PHENIX, and CRBR, alignment of the vertical sodium pump for the Clinch River Breeder Reactor Plant (CRBRP) is investigated. The CRBRP pump includes a flexibly coupled pump shaft and motor shaft, two oil-film tilting-pad hydrodynamic radial bearings in the motor plus a vertical thrust bearing, and two sodium hydrostatic bearings straddling the double-suction centrifugal impeller in the pump.
Date: January 1, 1981
Creator: Gupta, V.K. & Fair, C.E.
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

Three-dimensional finite-element analysis of the cellular convection phenomena in the Clinch River Breeder Reactor Plant prototype pump

Description: Cellular convection was studied rigorously during the development of the Clinch River Breeder Reactor Plant (CRBRP) Program Pumps. This paper presents the development of a three-dimensional finite-element heat transfer model which accounts for the cellular convection phenomena. A buoyancy driven cellular convection flow pattern is introduced in the annulus region between the upper inner structure and the pump tank. Steady-state thermal data were obtained for several test conditions for argon gas pressures up to 93 psig (741 kPa) and sodium operating temperatures to 1000/sup 0/F (811/sup 0/K). Test temperature distributions on the pump tank and inner structure were correlated with numerical results and excellent agreement was obtained.
Date: January 1, 1983
Creator: Silver, A.H. & Lee, J.Y.
Partner: UNT Libraries Government Documents Department

Contribution of Clinch River Breeder Reactor plant design and development to the LMFBR fuel cycle

Description: This paper describes how the CRBRP development and CRBRP focus of the LMFBR base technology program have led to advances in the state of the art in physics, thermal-hydraulics, structural analysis, core restraint, seismic analysis, and analysis of hypothetical core-disruptive accident energetics, all of which have been incorporated through disciplined engineering into the final CRBRP design. The total development in the US of fuels and materials, the analytical advances made on CRBRP design, and the incorporation of the latest experimental results into that design have put the US technology in general and the CRBRP design in particular at the forefront of technology. This has placed the US in a position to develop the most favorable LMFBR fuel cycle.
Date: January 1, 1981
Creator: Riley, D.R. & Dickson, P.W.
Partner: UNT Libraries Government Documents Department

Confirmation of the calculated breeding ratio for CRBRP

Description: A breeding ratio of at least 1.2 was a design goal for CRBRP. The value for the initial core (using plutonium with 11% /sup 240/Pu) calculated with ENDF/B-IV data is 1.27. Engineering mock-up studies for CRBRP were made in ZPPR-11. Analysis of ZPPR-11 using ENDF/B-IV data showed consistent underprediction of K/sub eff/ by about 1.5% and overpredictions of the /sup 238/U capture to /sup 239/Pu fission ratio (C8/F9) between 5% and 8%. These results are typical for all LMFBR critical assemblies at ANL. The following approach was used to determine the breeding ratio: sensitivity analysis of a range of fast reactor benchmarks and a fit to the experimental data by data adjustment; tests of the adjusted data against experiments in ZPPR-11; calculations for CRBRP with ENDF/B-IV data and the adjusted data to predict the breeding ratio bias; and estimates of k/sub eff/ and breeding ratio uncertainties using data sensitivities for CRBRP.
Date: January 1, 1983
Creator: Collins, P.J.; Liaw, J. & Turski, R.
Partner: UNT Libraries Government Documents Department

Cell liner design for LMFBR plants

Description: Those areas or cells within LMFBR plants that contain radioactive sodium systems are provided with certain design features which eliminate or limit potential sodium/concrete reaction and thus protect the concrete structure in the event of an accidental sodium spill. The principal design feature within these cells that controls sodium spill effects is the cell liner system. The development of such a system design for the Clinch River Breeder Reactor Plant (CRBRP) is presented in this paper. The basis for cell liner designs is described, including general design criteria, materials and welding requirements, system design requirements, load categories and loading combinations and allowable stress and strain levels. Results of stress analysis and design details of the cell wall and floor systems are presented, including provisions for protection of the concrete structure against high temperature effects.
Date: January 1, 1978
Creator: Palm, R.E. & Burrow, R.C.
Partner: UNT Libraries Government Documents Department

CRBRP sodium circulating pump design evaluation

Description: The following topics are discussed: (1) primary sodium pump design concept; (2) pump level control system; (3) resolution of design problems in stress analysis, dynamics analysis, and mechanical design; (4) model testing; (5) planned performance tests; and (6) fabrication status. (DG)
Date: December 1, 1977
Creator: Marrujo, F.; Cook, M.; Manners, L. & Cothran, H.
Partner: UNT Libraries Government Documents Department

Parameter sensitivity study in the dynamic simulation of a sodium cooled breeder reactor power plant

Description: The time domain sensitivity measure, peak sensitivity, was employed in studying the dynamics of a Clinch River Breeder Reactor Power Plant (CRBRP) digital simulator. With its use the most ''safety sensitive'' parameters in the plant model were identified for particular anticipated transients. Examples of such parameters include the Doppler feedback coefficient, fraction of power generated in the core, and the two phase flow friction multiplier. A method of putting first order bounds on a particular power plant transient due to parameter estimate error is also presented. This information is valuable since the CRBRP simulator was constructed with the intent of studying the safety of the system.
Date: January 1, 1978
Creator: Kolb, G.J.
Partner: UNT Libraries Government Documents Department

Design and development of the CRBRP ex-vessel transfer machine

Description: The Reactor Refueling System (RRS) for the Clinch River Breeder Reactor Project (CRBRP) uses the Ex-Vessel Transfer Machine (EVTM) for transferring core assemblies outside the reactor vessel. The design of the Ex-Vessel Transfer Machine (EVTM) and its gantry-trolly for the CRBRP is discussed. The development tests required for the design are presented, in conjunction with the impact of the test results on the design. The impact of the increased seismic requirements on the design are also presented.
Date: January 1, 1977
Creator: Jones, C.E. Jr.
Partner: UNT Libraries Government Documents Department

Signal analysis method using cross-correlation of turbulence flow signals to determine calibration of permanent magnet sodium flowmeters

Description: Permanent magnet flowmeters are used to measure flow in sodium cooled power plants both in the core and in plant piping. In this paper the cross-correlation technique and in particular the transfer function method is used to process the flow turbulence signals from electrodes spaced along the pipe in the vicinity of the magnetic field. Results from a loop flowmeter the EBR-II secondary flowmeter and a 400 mm diameter flowmeter are presented.
Date: January 1, 1977
Creator: Raptis, A.C. & Forster, G.A.
Partner: UNT Libraries Government Documents Department

Theoretical evaluation of ex-vessel monitoring for initial fuel loading of a liquid metal fast breeder reactor

Description: Transport theory calculations were used to determine the feasibility of monitoring the fuel loading to initial criticality of the Clinch River Breeder Reactor (CRBR) with a detector in a cavity outside the reactor vessel. Such monitoring of the CRBR with an ex-vessel detector will be different from monitoring of previous LMFBRs, where in-vessel detectors were used. The feasibility of ex-vessel monitoring will depend mainly on two criteria: (1) sensitivity - will there be enough counts to obtain adequate counting statistics; and (2) interpretability - will the count rate obtained during the initial fuel loading sequence be sufficient to determine the neutron multiplication or reactivity. Satisfying these criteria will assure that the reactor can be loaded safely to initial criticality. The sensitivity criterion can be satisfied by inserting an additional neutron source (one much more intense than the inherent neutron source of the fuel subassemblies) into the core center and using ex-vessel detectors with high sensitivity, such as multiple BF/sub 3/ counters mounted in a graphite moderator block. These calculations were used to determine the intensity of the additional source required to produce adequate counting rates at the ex-vessel detectors.
Date: January 1, 1979
Creator: Mihalczo, J.T.; Selby, D.L. & Knee, H.E.
Partner: UNT Libraries Government Documents Department

Design of the upper internals structure for the Clinch River Breeder Reactor Plant

Description: The Upper Internals Structure (UIS) is located above the core and is supported from the head at four locations. It is designed to perform the following primary functions: provide secondary core holddown in the event of a malfunction of the core hydraulic holddown system; provide support for routing all in-vessel instrumentation to core assemblies; maintain alignment between the core assemblies, the UIS and the closure head; provide guidance and crossflow protection for the control rod drivelines; and mix/duct flow to the upper region of the vessel outlet plenum to minimize rapid temperature changes to components during a reactor trip transient. In accomplishing these functions, the UIS will experience a sodium environment with temperatures up to 1200/sup 0/F (649/sup 0/C), and as many as 7 x 10/sup 8/ cycles of fluid temperature fluctuations up to 250/sup 0/F (121/sup 0/C) at full power operation. It must be designed to survive these conditions in combination with seismic and flow-induced vibration loadings for its 30 year design life. The design program of designing to controlled functional requirements and design conditions is discussed. Included is a description of the significant parts of the design and the approach used to balance the requirement of tight joints. The thermal and hydraulic environment including the results of a comprehensive test program are discussed. The test program results establish the basis of the thermal boundary used in the structural evaluation, and the UIS vibration characteristics. A summary of the areas which have required design changes is included with a summary of the structural evaluation of these changes.
Date: January 1, 1977
Creator: Thompson, D. C. & Novendstern, E. H.
Partner: UNT Libraries Government Documents Department