title: Control rod drop surveillance using two friction coefficients
creator: Blázquez, Juan
creator: Vallejo, I.
creator: García-Berrocal Sánchez, Agustin
creator: Balbás Antón, Miguel
subject: Physics
description: In the case of large burnup, a control rod (CR) guide tube in the pressurized water reactor of a commercial nuclear power plant might bend. As a consequence, a CR drop experiment may indicate an event of a CR partially inserted and whether the CR should be deemed inoperable. Early prevention of such an event can be achieved by measuring two friction coefficients: the hydraulic coefficient and the sliding coefficient. The hydraulic coefficient hardly changes, so that the curvature of the guide tube can only be detected thanks to a variation of the sliding coefficient. A simple model for the CR drop is established and validated with CR drop experiments. If tmx denotes the instant of CR maximum velocity, a linear relationship between (tmx)_2 and the sliding coefficient is found.
publisher: E.T.S.I. Minas (UPM)
rights: https://creativecommons.org/licenses/by-nc-nd/3.0/es/
date: 2011-11
type: info:eu-repo/semantics/article
type: Article
source: Nuclear Technology, ISSN 0029-5450, 2011-11, Vol. 176, No. 2
type: PeerReviewed
format: application/pdf
language: eng
relation: http://www.ans.org/store/j_13302
rights: info:eu-repo/semantics/restrictedAccess
identifier: https://oa.upm.es/15313/