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Spallator - accelerator breeder

Description: The concept involves the use of spallation neutrons produced by interaction of a high energy proton (1 to 2 GeV) from a linear accelerator (LINAC) with a heavy metal target (uranium). The principal spallator concept is based on generating fissile fuel for use in LWR nuclear power plants. The spallator functions in conjunction with a reprocessing plant to regenerate and produce the Pu-239 or U-233 for fabrication into fresh LWR reactor fuel elements. Advances in proton accelerator technology has provided a solid base for predicting performance and optimizing the design of a reliable, continuous wave, high-current LINAC required by a fissile fuel production machine.
Date: January 1, 1985
Creator: Steinberg, M.
Partner: UNT Libraries Government Documents Department

Physics and feasibility study of the Fast-Mixed Spectrum Reactor concept

Description: Reactor physics and fuel cycle studies, coordinated with heat transfer and material science and structural analysis work has indicated the feasibility potential of the coupled Fast-Mixed Spectrum Reactor (FMSR) concept. This concept employs what are considered reasonable extrapolations of present fast breeder reactor technology to achieve a once-through-and-store reactor fuel cycle. Since the fuel cycle for this reactor is intended to use only natural or depleted uranium for its equilibrium feed, the resultant reactor would have excellent anti-proliferation characteristics. It would also extend utilization of natural uranium resources by a factor of about 15 relative to LWR reactors when on its equilibrium fuel cycle; startup requirements would of course reduce this factor.
Date: January 1, 1979
Creator: Fischer, G.J.; Kouts, H.J.C.; Cerbone, R.J.; Shenoy, S.; Durston, C.; Ludewig, H. et al.
Partner: UNT Libraries Government Documents Department

Experiences with fast breeder reactor education in laboratory and short course settings

Description: The breeder reactor industry throughout the world has grown impressively over the last two decades. Despite the uncertainties in some national programs, breeder reactor technology is well established on a global scale. Given the magnitude of this technological undertaking, there has been surprisingly little emphasis on general breeder reactor education - either at the university or laboratory level. Many universities assume the topic too specialized for including appropriate courses in their curriculum - thus leaving students entering the breeder reactor industry to learn almost exclusively from on-the-job experience. The evaluation of four course presentations utilizing visual aids is presented.
Date: January 17, 1983
Creator: Waltar, A.E.
Partner: UNT Libraries Government Documents Department

Time-series investigation of anomalous thermocouple responses in a liquid-metal-cooled reactor

Description: A study was undertaken using SAS software to investigate the origin of anomalous temperature measurements recorded by thermocouples (TCs) in an instrumented fuel assembly in a liquid-metal-cooled nuclear reactor. SAS macros that implement univariate and bivariate spectral decomposition techniques were employed to analyze data recorded during a series of experiments conducted at full reactor power. For each experiment, data from physical sensors in the tests assembly were digitized at a sampling rate of 2/s and recorded on magnetic tapes for subsequent interactive processing with CMS SAS. Results from spectral and cross-correlation analyses led to the identification of a flow rate-dependent electromotive force (EMF) phenomenon as the origin of the anomalous TC readings. Knowledge of the physical mechanism responsible for the discrepant TC signals enabled us to device and justify a simple correction factor to be applied to future readings.
Date: March 24, 1988
Creator: Gross, K.C.; Planchon, H.P. & Poloncsik, J.
Partner: UNT Libraries Government Documents Department

Ex-vessel core catcher design requirements and preliminary concepts evaluation. [LMFBR]

Description: As part of the overall study of the consequences of a hypothetical failure to scram following loss of pumping power, design requirements and preliminary concepts evaluation of an ex-vessel core catcher (EVCC) were performed. EVCC is the term applied to a class of devices whose primary objective is to provide a stable subcritical and coolable configuration within containment following a postulated accident in which it is assumed that core debris has penetrated the Reactor Vessel and Guard Vessel. Under these assumed conditions a set of functional requirements were developed for an EVCC and several concepts were evaluated. The studies were specifically directed toward the FFTF design considering the restraints imposed by the physical design and construction of the FFTF plant.
Date: June 14, 1974
Creator: Friedland, A.J. & Tilbrook, R.W.
Partner: UNT Libraries Government Documents Department

COVERX service module of the FORSS system. [LMFBR]

Description: The COVERX Service Module includes seven execution paths to aid in understanding and using multigroup cross-section covariance matrices contained in the standard interface file COVERX. The execution paths provide the following operations on COVERX file(s): list the contents of a COVERX file; allow adding new multigroup cross-section covariance matrices to an existing COVERX file; allow deletion of multigroup covariance matrices from an existing COVERX file; merge two COVERX files and creates a new file; change the mode of a file from unformatted to formatted and conversely; allow modification of the records contained in a COVERX file; and selectively edits or copies a file.
Date: April 1, 1980
Creator: Drischler, J.D.
Partner: UNT Libraries Government Documents Department

Core design and optimization of high performance low sodium void 1000 MWe heterogeneous oxide LMFBR cores

Description: Radially heterogeneous core configurations are effective means to reduce sodium void reactivity. In general, radially heterogeneous cores can be designed as tightly or loosely coupled cores with center core or center blanket arrangements. Core height, number of core regions and number of fuel pins per assembly are additional variables in an optimization of basic heterogeneous core configurations. An extensive study was carried out to optimize the core configurations for 1000 MWe LMFBRs. All cores were subject to a common set of nuclear, mechanical, and thermal-hydraulic design assumptions. They were restrained by an upper sodium void reactivity limit of $2.50 and a doubling time of approximately 15 to 18 years. The screening and optimization procedures employed lead to two core layouts which were both tightly coupled. A complete nuclear analysis of these two cores (derived from a loosely coupled configuration/derived from a tightly coupled configuration) determined the fissile inventories (4268.4/4213.4 kg at BOEC), burnups (83.90/100.7 MWd/t peak), reactivity swings (0.49/1.8% ..delta..k total), power and flux distributions for different control insertion patterns, the breeding performance (15.7/15.3 yrs CSDT), the safety parameters, such as sodium void reactivity ($2.38/$2.23 at EOEC), isothermal Doppler coefficients for both sodium-in (45.6/46.1 T dk/dT x 10/sup -4/ core at EOEC) and sodium-out conditions (28.6/28.2 T dk/dT x 10/sup -4/ core at EOEC), and the transient behavior which shows very little space-dependence during a 60 cent reactivity step insertion.
Date: January 1, 1979
Creator: Barthold, W.P.; Orechwa, Y.; Su, S.F.; Beitel, J.C.; Turski, R.; Lam, P.S.K. et al.
Partner: UNT Libraries Government Documents Department

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

Concept and preliminary design of double tubesheet connector region for design and steady-state conditions. [LMFBR]

Description: In this analysis the structural integrity of the double tubesheet connector for the LMFBR demonstration plant steam generator is investigated for design and steady state conditions. Although the evaporator and superheater are to be interchangeable, only the steam outlet end of the evaporator is investigated. This was selected because the mean temperature differences between the tubesheets, tubes and connector are largest here at steady state, thus yielding the highest thermal loads. Combined with the thermal loads are superheater pressures in order to also use the highest mechanical loads. Although this is a conservative approach for the evaporator, the superheater must be analyzed separately at a later date in order to assure interchangeability. Evaluation of the results is based upon ASME Code Case 1331-8.
Date: June 1, 1974
Creator: Rinne, W.A.
Partner: UNT Libraries Government Documents Department

Analysis of SBTF quadelliptical furnaces. [LMFBR]

Description: A computer model was developed which predicts the axial temperature profile and heat flux at the outer surface of the test section of the Sodium Boiling Test Facility constructed by the Engineering Technology Division at ORNL. The model was in agreement with observed temperature profiles at furnace power levels representative of single phase, dual phase, and dry-out operations. A parametric study demonstrated the effect of sodium flow rate and surface emissivities on the predicted temperature profile. It was concluded that axial conduction in the Hastelloy tube and sodium must be incorporated into the model to improve accuracy.
Date: February 23, 1979
Creator: Anderson, F.E. & Schulz, R.B.
Partner: UNT Libraries Government Documents Department

Analysis of fission-product effects in a Fast Mixed-Spectrum Reactor concept

Description: The Fast Mixed-Spectrum Reactor (FMSR) concept has been proposed by BNL as a means of alleviating certain nonproliferation concerns relating to civilian nuclear power. This breeder reactor concept has been tailored to operate on natural uranium feed (after initial startup), thus eliminating the need for fuel reprocessing. The fissile material required for criticality is produced, in situ, from the fertile feed material. This process requires that large burnup and fluence levels be achievable, which, in turn, necessarily implies that large fission-product inventories will exist in the reactor. It was the purpose of this study to investigate the effects of large fission-product inventories and to analyze the effect of burnup on fission-product nuclide distributions and effective cross sections. In addition, BNL requested that a representative 50-group fission-product library be generated for use in FMSR design calculations.
Date: February 1, 1980
Creator: White, J.R. & Burns, T.J.
Partner: UNT Libraries Government Documents Department

Analytical approach for confirming the achievement of LMFBR reliability goals

Description: The approach, recommended by GE-ARSD, for confirming the achievement of LMFBR reliability goals relies upon a comprehensive understanding of the physical and operational characteristics of the system and the environments to which the system will be subjected during its operational life. This kind of understanding is required for an approach based on system hardware testing or analyses, as recommended in this report. However, for a system as complex and expensive as the LMFBR, an approach which relies primarily on system hardware testing would be prohibitive both in cost and time to obtain the required system reliability test information. By using an analytical approach, results of tests (reliability and functional) at a low level within the specific system of interest, as well as results from other similar systems can be used to form the data base for confirming the achievement of the system reliability goals. This data, along with information relating to the design characteristics and operating environments of the specific system, will be used in the assessment of the system's reliability.
Date: September 30, 1981
Creator: Ingram, G.E.; Elerath, J.G. & Wood, A.P.
Partner: UNT Libraries Government Documents Department

Scoping systems analysis of a 350 MWt modular liquid metal cooled reactor

Description: The systems analysis code SASSYS was used to explore the sensitivity of the system response to various inherent reactivity feedback mechanisms and design features for a small, liquid-metal-cooled reactor during the first 1000 s following the initiation of an unprotected loss-of-flow and/or loss-of-primary-heat-removal transient. The results show that to maximize the inherent safety of small, liquid-metal-cooled reactors, inherent feedback mechanisms should be accounted for in establishing design features such as the flow coastdown time constant and the control rod suspension system. The results also indicate insensitivity of the system response to the operation or non-operation of heat removal systems during the early part of an unprotected loss-of-flow transient.
Date: January 1, 1985
Creator: Morris, E.E.; Rhow, S.K. & Switick, D.M.
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

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

Evaluation of the magnitude and effects of bundle duct interaction in fuel assemblies at developmental plant conditions

Description: Purpose of this evaluation is to estimate the magnitude and effects of irradiation and creep induced fuel bundle deformations in the developmental plant. This report focuses on the trends of the results and the ability of present models to evaluate the assembly temperatures in the presence of bundle deformation. Although this analysis focuses on the developmental plant, the conclusions are applicable to LMFBR fuel assemblies in general if they have wire spacers.
Date: September 1, 1980
Creator: Serell, D.C. & Kaplan, S.
Partner: UNT Libraries Government Documents Department

Hydrogen meter for service in liquid sodium

Description: This standard establishes the requirements for the design, materials, fabrication, quality assurance, examination, and acceptance testing of a hydrogen meter and auxiliary equipment for use in radioactive or nonradioactive liquid sodium service. The meter shall provide a continuous and accurate indication of the hydrogen impurity concentration over the range 0.03 to 10 ppM hydrogen in sodium at temperatures between 800 and 1000/sup 0/F (427 and 538/sup 0/C). The meter may also be used to rapidly monitor changes in hydrogen concentration, over the same concentration range, and, therefore can be used as a sensor for sodium-water reactions in LMFBR steam generators.
Date: November 1, 1983
Creator: McCown, J J
Partner: UNT Libraries Government Documents Department

Determination of statistically based design limits associated with engineering models. (LWBR Development Program)

Description: This report provides a usable reference of methods and procedures for the construction of both one-sided and two-sided ..gamma../P statistical tolerance limits for design application to both linear and nonlinear models in any number of variables.
Date: February 1, 1980
Creator: Ginsburg, H.
Partner: UNT Libraries Government Documents Department

GCFR shielding design and supporting experimental programs

Description: The shielding for the conceptual design of the gas-cooled fast breeder reactor (GCFR) is described, and the component exposure design criteria which determine the shield design are presented. The experimental programs for validating the GCFR shielding design methods and data (which have been in existence since 1976) are also discussed.
Date: May 1, 1980
Creator: Perkins, R.G.; Hamilton, C.J. & Bartine, D.
Partner: UNT Libraries Government Documents Department

Input parameters to codes which analyze LMFBR wire-wrapped bundles

Description: This report provides a current summary of recommended values of key input parameters required by ENERGY code analysis of LMFBR wire wrapped bundles. This data is based on the interpretation of experimental results from the MIT and other available laboratory programs.
Date: December 1, 1980
Creator: Hawley, J.T.; Chan, Y.N. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department

Input parameters to codes which analyze LMFBR wire wrapped bundles. Revision 1

Description: This report provides a current summary of recommended values of key input parameters required for ENERGY code analysis of LMFBR wire wrapped bundles. This data is based on the interpretation of experimental results from the MIT and other available laboratory programs.
Date: May 1, 1979
Creator: Wang, S.F. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department

Analysis of Flow Impedance Phenomena. Final report, June 1, 1978-July 31, 1979. [LMFBR]

Description: Pressure drop data obtained during testing of the MARK I, II and IIA fuel assemblies in the Argonne National Laboratory liquid metal core component loop (CCTL) were analyzed. It is concluded that the previously unexplained pressure drop increase measured across the MARK II and MARK IIA assemblies was caused by metallic particulate fouling; the source was mechanical-chemical wear of the loops pump journal shaft. The implication to liquid metal breeder reactor (LMFBR) operation is that if a continuous source of metallic particles exists upstream of the core, a pressure drop increase can be expected. The size of the deposited particles should be larger than the thickness of laminar sublayer on a fuel rod. It is also concluded that the most probable source of metallic particulates will come from component failure and not from normal corrosion products. A small amount of deposited particulates can produce a relatively high pressure drop increase.
Date: December 1, 1979
Creator: Bishop, A. A.
Partner: UNT Libraries Government Documents Department