Download or read book Nonlinear Sensitivity and Uncertainty Analysis in Support of the Blowdown Heat Transfer Program Test 177 at Thermal Hydraulic Test Facility written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A nonlinear uncertainty analysis methodology based on the use of first and second order sensitivity coefficients is presented. As a practical demonstration, an uncertainty analysis of several responses of interest is performed for Test 177, which is part of a series of tests conducted at the Thermal-Hydraulic Test Facility (THTF) of the ORNL Engineering Technology Division Pressurized Water Reactor-Blowdown Heat Transfer (PWR-BDHT) program. These space- and time-dependent responses are: mass flow rate, temperature, pressure, density, enthalpy, and water qualtiy - in several volumetric regions of the experimental facility. The analysis shows that, over parts of the transient, the responses behave as linear functions of the input parameters; in these cases, their standard deviations are of the same order of magnitude as those of the input parameters. Otherwise, the responses exhibit nonlinearities and their standard deviations are considerably larger. The analysis also shows that the degree of nonlinearity of the responses is highly dependent on their volumetric locations.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 780 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 1652 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Regulatory and Technical Reports written by U.S. Nuclear Regulatory Commission. Policy and Publications Management Branch and published by . This book was released on 1981 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Regulatory and Technical Reports written by U.S. Nuclear Regulatory Commission. Division of Technical Information and Document Control and published by . This book was released on 1980 with total page 596 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes indexes.
Download or read book PWR Blowdown Heat Transfer Separate Effects Program Thermal Hydraulic Test Facility Experimental Data Report for Test 167R written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 167R, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 167R was conducted to obtain thermal-hydraulic and CHF information in THTF bundle 1 with an intact cold leg. The primary purpose of this report is to make the reduced instrument responses during test 167R available. These are presented in graphical form in engineering units and have been analyzed only to the extent necessary to ensure reasonableness and consistency.
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1981 with total page 666 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book PWR Blowdown Heat Transfer Separate Effects Program written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 101, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 101 was conducted to investigate the thermal-hydraulic response of bundle 1 and the main heat exchangers to powered operation and a single-ended rupture at the test section outlet.
Download or read book Project Description written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The ORNL Pressurized-Water Reactor Blowdown Heat Transfer (PWR-BDHT) Program is an experimental separate-effects study of the relations among the principal variables that can alter the rate of blowdown, the presence of flow reversal and rereversal, time delay to critical heat flux, the rate at which dryout progresses, and similar time-related functions that are important to LOCA analysis. Primary test results will be obtained from the Thermal-Hydraulic Test Facility (THTF), a large nonnuclear pressurized-water loop that incorporates a 49-rod electrically heated bundle. Supporting experiments will be carried out in two additional test loops - the Forced Convection Test Facility (FCTF), a small high-pressure facility in which single heater rods can be tested in annular geometry; and an air-water loop which is used to evaluate two-phase flow-measuring instrumentation.
Download or read book PWR Blowdown Heat Transfer Separated Effects Program Thermal Hydraulic Test Facility Experimental Data Report for Test 102 PWR written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 102, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 102 was conducted to investigate the thermal-hydraulic response of bundle 1 under full-power steady-state and blowdown conditions.
Download or read book Uncertainty Analysis of A Calibrated Hot Box written by S. Yuan and published by . This book was released on 2002 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The accuracy of the thermal transmittance, or U-factor, of a fenestration system measured in a building assembly thermal test facility depends upon the test apparatus, test conditions, operating procedure, and the specimen properties. By conducting the uncertainty analysis of a specific thermal test facility, the measurement uncertainty can be identified and quantified. The estimation procedure for the uncertainty associated with the U-factor result for a test apparatus should be established and reported with the measurement of the U-factors of fenestration products. In a study on the University of Massachusetts Research Calibrated Hot Box, detailed analyses of the elemental uncertainties associated with the basic measurements and uncertainty propagation on U-factor results have been performed. In the analysis of uncertainty ropagation, the Root Sum Square (RSS) method was used extensively. The procedure for uncertainty analysis used for this test apparatus can be used in any ASTM C 1363 hot box thermal test facility including those also using ASTM C 1199 for fenestration U- factor measurements. Using the uncertainty analysis procedure described in detail in this paper, a plastic-faced Calibration Standard Transfer (CTS) is analyzed. The results show a reasonable uncertainty level for the U-factor measurement made using ASTM C 1199.The improvement of the U-factor uncertainty can be achieved by reducing the uncertainties associated with the test specimen flanking heat transfer and the metering chamber extraneous heat transfer in the hot box test apparatus.
Download or read book Analysis of GE BWR Blowdown Heat Transfer Program written by Electric Power Research Institute and published by . This book was released on 1975 with total page 69 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis of Standard Problem Six Semiscale Test S 02 6 Data PWR written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Test S-02-6 of the Semiscale Mod-1 blowdown heat transfer test series was conducted to supply data for the U.S. Nuclear Regulatory Commission Standard Problem Six. To determine the credibility of the data and thus establish the validity of Standard Problem Six, an analysis of the results of Test S-02-6 was performed and is presented. This analysis consisted of investigations of system hydraulic and core thermal data. The credibility of the system hydraulic data was investigated through comparisons of the data with data and calculations from related sources (Test S-02-4) and, when necessary, through assessment of physical events. The credibility of the core thermal data was based on a thorough analysis of physical events. The results of these investigations substantiate the validity of Test S-02-6 data.
Download or read book Sensitivity Theory Applied to a Transient Thermal hydraulics Problem written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A new method for sensitivity analysis of transient nonlinear problems is developed and applied to a reactor thermal-hydraulics problem. The method resembles the differential sensitivity methods currently used in the linear problems of reactor physics, but it is applicable to nonlinear systems as well. The equations governing heat transfer and fluid flow in a fuel pin and surrounding coolant are given and used to derive a second set of equations (commonly known as the adjoint equations) used in the sensitivity analysis. Both systems contain one second-order parabolic and one first-order hyperbolic partial differential equation. Difference equations are derived to approximate both systems and the convergence properties of these discrete systems are evaluated, yielding a useful analysis of the numerical solution. The solution functions are used to derive sensitivity coefficients for any desired integral response. These sensitivity coefficients are used in a first-order perturbation theory to predict changes in a response resulting from changes in parameter values. The results of a test problem are shown, verifying that this procedure is indeed useful for a wide variety of sensitivity calculations.
Download or read book Semiscale Mod 1 Program and System Description for the Blowdown Heat Transfer Tests test Series 2 written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Regulatory Commission Issuances written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1979 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal Hydraulics of Water Cooled Nuclear Reactors written by Francesco D'Auria and published by Woodhead Publishing. This book was released on 2017-05-18 with total page 1200 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants
