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control rod

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control rod

[kən′trōl ‚räd]
(nucleonics)
Any rod used to control the reactivity of a nuclear reactor; may be a fuel rod or part of the moderator; in a thermal reactor, commonly a neutron absorber. Also known as absorbing rod.
McGraw-Hill Dictionary of Scientific & Technical Terms, 6E, Copyright © 2003 by The McGraw-Hill Companies, Inc.

control rod

control rod
A push-pull rod for actuating controls from the cockpit. Control rods are used in manually operated flight control systems.
An Illustrated Dictionary of Aviation Copyright © 2005 by The McGraw-Hill Companies, Inc. All rights reserved
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References in periodicals archive
The drop time of the control rod was evaluated based on its weight and the small pressure difference between the moderator (0.3 MPa) and the containment (atmospheric pressure of 0.1 MPa).
Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics
In the real-world conditions, control rod channel water inlet temperature is about 40[degrees]C and outlet temperature is around 70[degrees]C.
Numerical simulation of foam flow through RBMK-1500 control rod channel/RBMK-1500 reaktoriaus valdymo strypo kanalo ausinimo putu srautu sumodeliavimas
Criticality calculations of the core with four control rod banks have been carried out.
Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5
The control rod assembly has transverse vibration under flow excitation.
R&D on a Nonlinear Dynamics Analysis Code for the Drop Time of the Control Rod
The second case is induced by a control rod withdrawal out of core by mistake.
Three Design Basis Accidents' Analysis on the HTR-10GT
In addition, in order to study the core performance under normal and accident conditions, it is also necessary to investigate the fundamental properties of nuclear reactor core besides the neutron economy analysis, such as moderator and fuel temperature coefficients, control rods worth, radial power distribution, and different void reactivity coefficients.
Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination [U.sub.3][Si.sub.2]-FeCrAl
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