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Title: Modeling and Experimental Tests on the Hydraulically Driven Control Rod option for IRIS Reactor

Abstract

The adoption of Internal Control Rod Drive Mechanisms (ICRDMs) represents a valuable alternative to classical, external CRDMs based on electro-magnetic devices, as adopted in current PWRs. The advantages on the safety features of the reactor are apparent: inherent elimination of the Rod Ejection accidents and of possible concerns about the vessel head penetrations. A further positive feedback on the design is the reduction of the primary system overall dimensions. Within the frame of the ICRDM concepts, the Hydraulically Driven Control Rod solution is investigated as a possible option for the IRIS integral reactor. After a brief comparison of the solutions currently proposed for integral reactors, the configuration of the Hydraulic Control Rod device for IRIS, made up by an external movable piston and an internal fixed cylinder, is described. A description of the whole control system is reported as well. Particular attention is devoted to the Control Rod profile characterization, performed by means of a Computational Fluid Dynamics (CFD) analysis. The investigation of the system behavior has been carried out, including the dynamic equilibrium and its stability properties, the withdrawal and insertion step movement and the sensitivity study on command time periods. A suitable dynamic model has been set upmore » for the mentioned purposes: the models corresponding to the various Control Rod system devices have been written in an Object-Oriented language (Modelica), thus allowing an easy implementation of such a system into the simulator for the whole reactor. Finally, a preliminary low pressure, low temperature, reduced length experimental facility has been built. Tests on HDCR stability and operational transients have been performed. The results are compared with the dynamic system model and CFD simulation model, showing good agreement between simulations and experimental data. During these preliminary tests, the control system performed correctly, allowing stable dynamic equilibrium positions for the Control Rod and stable behavior during withdrawal and insertion steps. (authors)« less

Authors:
; ;  [1]
  1. Department of Nuclear Engineering, Politecnico di Milano, Via Ponzio, 34/3, 20133 Milano (Italy)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
21160788
Resource Type:
Conference
Resource Relation:
Conference: ICAPP'04: 2004 international congress on advances in nuclear power plants, Pittsburgh, PA (United States), 13-17 Jun 2004; Other Information: Country of input: France; 24 refs; Related Information: In: Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04, 2338 pages.
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; CONTROL ROD DRIVES; CONTROL SYSTEMS; EQUILIBRIUM; EQUIPMENT; FLUID MECHANICS; MATHEMATICAL SOLUTIONS; PWR TYPE REACTORS; ROD EJECTION ACCIDENTS; TEMPERATURE RANGE 0065-0273 K

Citation Formats

Cammi, Antonio, Ricotti, Marco E, and Vitulo, Alessia. Modeling and Experimental Tests on the Hydraulically Driven Control Rod option for IRIS Reactor. United States: N. p., 2004. Web.
Cammi, Antonio, Ricotti, Marco E, & Vitulo, Alessia. Modeling and Experimental Tests on the Hydraulically Driven Control Rod option for IRIS Reactor. United States.
Cammi, Antonio, Ricotti, Marco E, and Vitulo, Alessia. Thu . "Modeling and Experimental Tests on the Hydraulically Driven Control Rod option for IRIS Reactor". United States.
@article{osti_21160788,
title = {Modeling and Experimental Tests on the Hydraulically Driven Control Rod option for IRIS Reactor},
author = {Cammi, Antonio and Ricotti, Marco E and Vitulo, Alessia},
abstractNote = {The adoption of Internal Control Rod Drive Mechanisms (ICRDMs) represents a valuable alternative to classical, external CRDMs based on electro-magnetic devices, as adopted in current PWRs. The advantages on the safety features of the reactor are apparent: inherent elimination of the Rod Ejection accidents and of possible concerns about the vessel head penetrations. A further positive feedback on the design is the reduction of the primary system overall dimensions. Within the frame of the ICRDM concepts, the Hydraulically Driven Control Rod solution is investigated as a possible option for the IRIS integral reactor. After a brief comparison of the solutions currently proposed for integral reactors, the configuration of the Hydraulic Control Rod device for IRIS, made up by an external movable piston and an internal fixed cylinder, is described. A description of the whole control system is reported as well. Particular attention is devoted to the Control Rod profile characterization, performed by means of a Computational Fluid Dynamics (CFD) analysis. The investigation of the system behavior has been carried out, including the dynamic equilibrium and its stability properties, the withdrawal and insertion step movement and the sensitivity study on command time periods. A suitable dynamic model has been set up for the mentioned purposes: the models corresponding to the various Control Rod system devices have been written in an Object-Oriented language (Modelica), thus allowing an easy implementation of such a system into the simulator for the whole reactor. Finally, a preliminary low pressure, low temperature, reduced length experimental facility has been built. Tests on HDCR stability and operational transients have been performed. The results are compared with the dynamic system model and CFD simulation model, showing good agreement between simulations and experimental data. During these preliminary tests, the control system performed correctly, allowing stable dynamic equilibrium positions for the Control Rod and stable behavior during withdrawal and insertion steps. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/21160788}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2004},
month = {7}
}

Conference:
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