Improving the Service Life and Performance of CANDU Fuel Channels PDF Download
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Author: A. R. Causey
Publisher: Chalk River, Ont. : Chalk River Laboratories
ISBN: 9780660164335
Category : CANDU reactors
Languages : en
Pages : 15
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Book Description
Author: A. R. Causey
Publisher: Chalk River, Ont. : Chalk River Laboratories
ISBN: 9780660164335
Category : CANDU reactors
Languages : en
Pages : 15
Get Book Here
Book Description
![Improving the Service Life and Performance of CANDU Fuel Channels [electronic Resource] PDF](https://books.google.com/books/content/images/frontcover/6ys2zgEACAAJ?fife=w80-h100)
Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Research and Product Development, Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages :
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Book Description
![Improving the Service Life and Performance of CANDU Fuel Channels [electronic Resource] PDF](https://books.google.com/books/content/images/frontcover/d5B6AQAACAAJ?fife=w80-h100)
Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Research and Product Development, Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages :
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Book Description
Author: Chalk River Nuclear Laboratories. Fuel Channel Components Branch
Publisher: Chalk River, Ont. : Fuel Channel Components Branch, Chalk River Laboratories
ISBN: 9780660168852
Category : CANDU reactors
Languages : en
Pages : 8
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Book Description
Author: B. Strachan
Publisher: Mississauga, Ont. : Atomic Energy of Canada Limited, CANDU Operations = Énergie atomique du Canada, limitée, Opérations CANDU
ISBN:
Category : Heavy water reactors
Languages : en
Pages : 17
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 15
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Book Description
Author: B. A. Cheadle
Publisher: Chalk River, Ont. : Reactor Materials Division, Chalk River Laboratories
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 56
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Book Description
Author: G. L. Brooks
Publisher:
ISBN:
Category :
Languages : en
Pages : 40
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Book Description
Author: R. H. Mills
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
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: E. D. Matias
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
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.
