An Evaluation of the influence of fuel design parameters and burnup on pellet/cladding interaction for boiling water reactor fuel rod through in-core diameter measurement

not registered

no abstracts in English

Language	:	English
Journal	:	Nuclear Technology
Volume	:	73
Number	:
Pages	:	p.361 - 377
Publication Year/Month	:	1986/00
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Paper URL	:	https://doi.org/10.13182/NT86-A16078
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	Fuel fabrication parameter; PCMI; Light water BWR fuel rod; In-core diameter measurement; Cladding deformation
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Accesses	:	- Accesses
Web of Science® Times Cited Count	:	Times Cited Count： If you would like to get the latest times cited, please access the Web of Science®. http://www.webofknowledge.com/wos
InCites™	:	Percentile:32.30 Category:Nuclear Science & Technology
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Registration No. : A19844128
JAEA Abstracts No. :
Paper Submission No. : 7737

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