Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Download Thermal Behaviour Of A Candu Phw Reactor Fuel Channel Containing Nearly Stagnant Steam full books in PDF, epub, and Kindle. Read online Thermal Behaviour Of A Candu Phw Reactor Fuel Channel Containing Nearly Stagnant Steam ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Author : G. E. Gillespie
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Thermal behaviour of a CANDU-phw reactor fuel channel containing nearly stagnant steam written by G. E. Gillespie and published by . This book was released on 1982 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : V. Q. Tang
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Chan ii : a computer program predicting fuel channel thermal behavior in a typical CANDU- phw reactor core following a loss-of-coolant accident written by V. Q. Tang and published by . This book was released on 1981 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 756 pages
Book Rating : 4.3/5 (129 download)
Download or read book Energy Research Abstracts written by and published by . This book was released on 1983 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Ahmet Durmayaz
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (85 download)
Download or read book A Loss-of-coolant Accident Analysis for Near Stagnation Flow in the Horizontal Fuel Channel of Candu Reactor written by Ahmet Durmayaz and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In this thesis, a two-phase thermalhydraulic model has been developed inorder to investigate the near stagnation flow phenomena in the horizontal fuelchannel of a CANDU nuclear reactor following a postulated small break _loss-_of-çoolant-accident (LOCA) in the inlet feeder or inlet header. In this model, the unequal velocity unequal temperature (UVUT) modelis used in which the velocities and enthalpies (hence temperatures) for both liquidand vapor phases, void fraction and a common dynamic pressure are computed. Stratified smooth and dispersed bubbly flows are considered together for the near stagnation flow and dispersed bubbly flow is considered for the normal operating conditions of a CANDU reactor as the flow regimes. Geometrical configuration of a typically CANDU reactor fuel channel is considered. Thermodynamic andtransport properties of heavy water are also considered as functions of pressure and temperature. In the derivations of the conservation equations, all of the terms are area and time (ensemble) averaged. A fully implicit discretization method and a staggered grid control volume approach are applied in order to obtain an algebraic equation set from the governing differential conservation equations. Hvbrid scheme. in which central difference and upwind schemes are considered by turns depending on the value of Peclet number, is used while deriving the discretization equations. To solve the near stagnation flow problem by using this model, the IPSA algorithm (Inter-Phase Slip Algorithm) which was developed to solve the multi-phase flows originally is modified to give a solution for a horizontal channel which is full of single phase fluid in some part whereas it is full of two- phase fluid in the other part. A computer code that is called as the ANESTA ( Analysis for NEar STAgnation flow in the fuel channel of a CANDU reactor ) code has been developed. The model mentioned above is applied to both normal operating conditions and the near stagnation flow (LOCA) conditions by this code. A set of approximate functions for the fast calculation of the thermodynamic properties of heavy water (D20 ) has also been derived. For this aim, the data given in the steam tables for heavy water thermodynamic properties have been accurately and successfully fitted to the curves as functions of pressure and temperature in order to obtain some simple functions by usingthe least-square method.
Author : Mati Merilo
Publisher :
ISBN 13 :
Total Pages : 830 pages
Book Rating : 4.3/5 (91 download)
Download or read book Thermal-hydraulics of Nuclear Reactors written by Mati Merilo and published by . This book was released on 1983 with total page 830 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 720 pages
Book Rating : 4.:/5 ( download)
Download or read book Proceedings of the International Meeting on Thermal Nuclear Reactor Safety written by and published by . This book was released on 1983 with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : P. M. Mathew
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Thermal conductivity of CANDU steam generator tubing alloys written by P. M. Mathew and published by . This book was released on 1997 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this study is to evaluate the relative impact of the design parameters on bundle uranium mass and sheath strain and to re-evaluate the basis for the limitation on bundle mass due to an increase in bundle subchannel cross-sections. bundle uranium mass is determined by parameters that in turn affect the sheath strain during operation. this might affect sub-channel flow areas and affect the chf-ccp. the bundle uranium mass was assessed with electres and resulting sheath strains estimated for a candu 6 fuel channel operating at overpowers just at the trip set point of the reactor (onset of sheath dryout), a 14% power increase. the electres fuel modeling code is used to determine the relative impact on sheath strain of the design parameters that control uranium mass, namely, pellet density, diametral clearance, axial gap, and pellet face geometry (chamfer, dish depth, and land width). a limitation was placed on bundle uranium mass by new brunswick power. this came from a ccp evaluation showing that a candu 6 reactor, fuelled with bundles having average masses greater than 19.25 kg u, would have a net positive sheath strain over a fuel channel at the power for the onset of dryout, and therefore a ccp penalty. the calculations were based on steady bundle powers, operating in a fuel channel at ccp to a burnup of 168 mw middle dot h/kg u. at this burnup the strain calculation included a 14% power boost. these are indeed very conservative assumptions with a view to maximizing calculated sheath strains, without regard for fuel defect probability. for comparison, this study has produced electres strain calculations for high power channel power histories representative of 8 bundle shifts, also with a 14% power boost, operating at dryout.
Author :
Publisher :
ISBN 13 :
Total Pages : 760 pages
Book Rating : 4.:/5 ( download)
Download or read book Proceedings of the International Meeting on Thermal Nuclear Reactor Safety, Held at Chicago, IL, August 29-September 2, 1982 written by and published by . This book was released on 1983 with total page 760 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : D. G. Dalrymple
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book In-service eddy current inspection of tubes in CANDU steam generators and heat exchangers written by D. G. Dalrymple and published by . This book was released on 1994 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document consists of candu zr-2.5nb pressure tube inspection and operating data primarily for ontario hydro reactors. the data presented here represent the current contents of the in-reactor deformation database developed and maintained at ohrd/1/. it is intended for use in the understanding of the deformation behaviour of fuel channels in power reactors and in the derivation and fine-tuning of material creep and growth constants for the new deformation equations. in compiling and presenting the deformation and operating data of fuel channels the databse provides a statistical sample of the actual operating behaviour of components in candu power reactors. this sample may be used to detect any abnormal or unexpected effects and to provide a means of comparison between different power reactos. with the future addition of 600 mw and experimental reactor data, this information will play a key role in the development of a broader understanding of fuel channel behaviour in the ongoing process of extending the operating lives of candu reactors. this document represents the first issue of the information in the database in a 3-ring binder format. it is felt that this format will avoid the need to re-issue the entire document when new information becomes available. it will be the responsibility of ohrd to provide updates on a regular basis (most likely annually). the information is divided into three sections: the first section contains diametral expansion inspection data for individual fuel channels, the second contains the sag inspection data, and the third contains the reactor operating data. within each section are three subsections: a legend describing the tables, information on the source and processing of the data in the tables, and the tables of the data.
Author : D. G. Vandenberghe
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book A study of fuel channel and reactor core thermal behaviour during a postulated loec accident written by D. G. Vandenberghe and published by . This book was released on 1978 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 974 pages
Book Rating : 4.:/5 (31 download)
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1983 with total page 974 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : G. J. Phillips
Publisher :
ISBN 13 :
Total Pages : 1180 pages
Book Rating : 4.E/5 ( download)
Download or read book International Conference on Numerical Methods in Nuclear Engineering written by G. J. Phillips and published by . This book was released on 1983 with total page 1180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 968 pages
Book Rating : 4.F/5 ( download)
Download or read book INIS Atomindex written by and published by . This book was released on 1983 with total page 968 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : American Nuclear Society
Publisher :
ISBN 13 :
Total Pages : 234 pages
Book Rating : 4.3/5 (91 download)
Download or read book Proceedings of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, San Diego, California, U.S.A., February 2-6, 1986 written by American Nuclear Society and published by . This book was released on 1986 with total page 234 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. Z. Caplan
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Flow behaviour in a CANDU horizontal fuel channel from stagnant subcooled intial conditions written by M. Z. Caplan and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : V. I. Arimescu
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Burnup-dependent uo2 thermal conductivity degradation and its impact on CANDU fuel as extended burnup written by V. I. Arimescu and published by . This book was released on 1993 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document consists of candu zr-2.5nb pressure tube inspection and operating data primarily for ontario hydro reactors. the data presented here represent the current contents of the in-reactor deformation database developed and maintained at ohrd/1/. it is intended for use in the understanding of the deformation behaviour of fuel channels in power reactors and in the derivation and fine-tuning of material creep and growth constants for the new deformation equations. in compiling and presenting the deformation and operating data of fuel channels the databse provides a statistical sample of the actual operating behaviour of components in candu power reactors. this sample may be used to detect any abnormal or unexpected effects and to provide a means of comparison between different power reactos. with the future addition of 600 mw and experimental reactor data, this information will play a key role in the development of a broader understanding of fuel channel behaviour in the ongoing process of extending the operating lives of candu reactors. this document represents the first issue of the information in the database in a 3-ring binder format. it is felt that this format will avoid the need to re-issue the entire document when new information becomes available. it will be the responsibility of ohrd to provide updates on a regular basis (most likely annually). the information is divided into three sections: the first section contains diametral expansion inspection data for individual fuel channels, the second contains the sag inspection data, and the third contains the reactor operating data. within each section are three subsections: a legend describing the tables, information on the source and processing of the data in the tables, and the tables of the data.
Author :
Publisher :
ISBN 13 :
Total Pages : 756 pages
Book Rating : 4.:/5 (3 download)
Download or read book Energy Research Abstracts written by and published by . This book was released on 1983 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.
