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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

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

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

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

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

Friction factor correlation for 217 pin wire-wrap spaced LMFBR fuel assemblies

Description: Data from four independent water flow tests of 217 pin wire wrap spaced LMFBR fuel assemblies were analyzed and a friction factor correlation was developed. The data show that the mean friction factor varied little from one test to the next and the test statistics show that at a 3sigma confidence level, the uncertainty of predicting the friction factor is less than 1.7% from Reynolds numbers of 1000 to 100,000.
Date: April 1, 1981
Creator: Spencer, D.R. & Markley, R.A.
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

Integration of safety considerations into the design of GCFR safety systems

Description: Under DOE sponsorship, the GCFR Program is preparing a program to integrate reliability into the engineering and design of safety related systems, subsystems and components. This program is considered consistent with the NRC licensing position for CRBR which established a formal reliability objective for the prevention of core damage. The objective of the program is to provide assurance that reliability goals established for systems and subsystems are met consistent with the overall plant goals. Special consideration is given to components for which only a generic data base exists. Based on evaluations of past reliability test programs, it is concluded that full scale reliability test programs are not cost effective but that extended DV and S testing may be warranted in special circumstances. The major elements of the program, their relationship and benefits to the design of safety systems are discussed.
Date: October 1, 1979
Creator: Torri, A.; Kelley, A.P.; Emon, D.E. & Goetzmann, C.
Partner: UNT Libraries Government Documents Department

Finite deformation analysis of continuum structures with time dependent anisotropic elastic plastic material behavior (LWBR/AWBA Development Program)

Description: A finite element procedure is presented for finite deformation analysis of continuum structures with time-dependent anisotropic elastic-plastic material behavior. An updated Lagrangian formulation is used to describe the kinematics of deformation. Anisotropic constitutive relations are referred, at each material point, to a set of three mutually orthogonal axes which rotate as a unit with an angular velocity equal to the spin at the point. The time-history of the solution is generated by using a linear incremental procedure with residual force correction, along with an automatic time step control algorithm which chooses time step sizes to control the accuracy and numerical stability of the solution.
Date: March 1, 1980
Creator: Hutula, D.N.
Partner: UNT Libraries Government Documents Department

Effect of simulated thermal shield motion on nuclear instrument response: measurements and calculations (LWBR Development Program)

Description: An experiment has been performed to determine the effect of motion of a thermal shield on the neutron signal expected from ex-core detectors. Using a mockup of the LWBR reactor vessel, thermal shield, and core barrel in conjunction with a /sup 252/Cf neutron source, the change in detector signal with displacement of the various components was investigated. It was found that moving the thermal shield would produce a significant change in detector signal, although the effect was smaller than would be produced by moving the source and core barrel together. The results were substantiated by two-dimensional discrete-ordinate calculations.
Date: August 1, 1979
Creator: Schick, W.C. Jr.; Emert, C.J.; Shure, K. & Natelson, M.
Partner: UNT Libraries Government Documents Department

THORS: a high-temperature sodium test facility rated at 2. 0 MW. [LMFBR]

Description: The Thermal--Hydraulic Out-of-Reactor Safety (THORS) facility at Oak Ridge Naitonal Laboratory (ORNL) is a high-temperature sodium test facility operated for the United States Breeder Reactor Safety Program. The facility is primarily used for testing large simulated Liquid-Metal Fast Breeder Reactor (LMFBR) fuel subassemblies. The facility has recently been upgraded to provide a 2.0-MW test bundle power input and heat removal capability. A new test section, which will be capable of operating at 980/sup 0/C and which will accommodate a 217-pin bundle, has also been added. A 61-pin bundle is currently under test in the facility. A description of the test facility is presented, along with a brief summary of the 8-year operating history of this safety-related test facility.
Date: January 1, 1979
Creator: Gnadt, P.A.; Anderson, A.H.; Clapp, N.E.; Montgomery, B.H.; Collins, C.W. & Stulting, R.D.
Partner: UNT Libraries Government Documents Department