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Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor
Joint Authors
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2008, Issue 2008 (31 Dec. 2008), pp.1-7, 7 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2008-04-01
Country of Publication
Egypt
No. of Pages
7
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
The horizontal coolant channel is one of the important parts of primary heat transport system in PHWR type of reactors.
There are in all 392 channels in the core of Indian 540 MWe reactor.
Each channel houses 13 natural uranium fuel bundles and shielding and sealing plugs one each on either side of the channel.
The heavy water coolant flows through the coolant channel and carries the nuclear heat to outside the core for steam generation and power production in the turbo-generator.
India has commissioned one 540 MWe PHWR reactor in September 2005 and another similar unit will be going into operation very shortly.
For a complete dynamic study of the channel and its internals under the influence of high coolant flow, experimental and modeling studies have been carried out.
A good correlation has been achieved between the results of experimental and analytical models.
The operating life of a typical coolant channel typically ranges from 10 to 15 full-power years.
Towards the end of its operating life, its health monitoring becomes an important activity.
Vibration diagnosis plays an important role as a tool for life management of coolant.
Through the study of dynamic characteristics of the coolant channel under simulated loading condition, an attempt has been made to develop a diagnostics to monitor the health of the coolant channel over its operating life.
A study has been also carried out to characterize the fuel vibration under different flow condition.
American Psychological Association (APA)
Dharmaraju, N.& Rama Rao, A.. 2008. Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor. Science and Technology of Nuclear Installations،Vol. 2008, no. 2008, pp.1-7.
https://search.emarefa.net/detail/BIM-496972
Modern Language Association (MLA)
Dharmaraju, N.& Rama Rao, A.. Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor. Science and Technology of Nuclear Installations No. 2008 (2008), pp.1-7.
https://search.emarefa.net/detail/BIM-496972
American Medical Association (AMA)
Dharmaraju, N.& Rama Rao, A.. Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor. Science and Technology of Nuclear Installations. 2008. Vol. 2008, no. 2008, pp.1-7.
https://search.emarefa.net/detail/BIM-496972
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-496972