Author: Atomic Energy of Canada LimitedPublisher: Chalk River, Ont. : Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 32
Book Description
Examination of Garter Springs from CANDU Reactors
Author: Atomic Energy of Canada LimitedPublisher: Chalk River, Ont. : Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 32
Book Description
Assessment of the requirement to reposition garter springs in operating reactors
Author: J. T. DunnAnalysis of garter spring stresses for the Douglas Point reactor
Author: N. W. BrodieAssessment of carrier bundle tool capability for locating garter springs in four-spring channels
Author: R. J. CheadlePublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A severe-fuel-damage accident in candu (canada deuterium uranium) reactors can be triggered by a pipe break in the primary circuit, resulting in the release of radioactive fission products entrained within unflashed water aerosols. under these circumstances, the transport behaviour of the unflashed liquid aerosols determines the transport and deposition patterns of the entrained fission products. transport behaiour of the liquid aerosols is strongly dependent on the droplet size and on the droplet size distribution of the aerosols. aerosol transport codes are available to estimate the transport and deposition properties of aerosols under reactor accident conditions in the containment. these models, however, rely on an initial condition for the aerosol droplet size distribution. information on aerosol size distributions generated under flashing jet conditions is lacking in the literature. characterizing the aerosol size distribution created by flashing jets is therefore necessary. measurements of aerosol droplet size distributions are possible with phase-shift doppler anemometry (psda). the use of anemometry techniques requires procedural checks to ensure confidence in the measurements. this report describes errors in the bias and variance of psda particle size measurements for particles between 1 and 100 micro m. the calculations are substantiated by examining monodisperse populations of droplets between 1 and 110 micro m in diameter. under the measurement conditions examined, the maximum bias error calculated was 5 percent, whereas the absolute error in variance was constant at approximately 4 micro m. reproducibility was found to be within 10 percent for the entire droplet size range.
The examination of inconel garter springs removed from NPD fuel channels c08 and k05
Author: P. J. SimonsMICROSTRUCTURAL ANALYSIS OF HELIUM DISTRIBUTION IN NICKEL AND INCONEL X750
Author: Aseem Kirtiman Chauhan Publisher: Book Rivers
ISBN: 9355152418
Category : Antiques & Collectibles
Languages : en
Pages : 100
Book Description
Sections of this thesis have been submitted as multiauthored papers and abstracts in various conferences. The results in this study were presented at National and International Conferences
Wear and stress of CANDU garter spring spacers
Author: W. HartleyEnergy Research Abstracts
Author: Detection of garter springs in e-series pressure tubes
Author: S. P. SullivanPressurized Heavy Water Reactors
Author: Publisher: Elsevier
ISBN: 0128232595
Category : Science
Languages : en
Pages : 546
Book Description
Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs. Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties. Provides a complete reference dedicated to the latest research on Pressurized Heavy Water Reactors and their economic and environmental benefits Goes beyond CANDU reactors to analyze the popular German and Indian designs, as well as plant design in Korea, Romania, China and Argentina Spans all phases of the nuclear power plant lifecycle, from design, manufacturing, operation, maintenance and long-term operation