A nuclear reactor core is the portion of a nuclear reactor containing the nuclear fuel components where the nuclear reactions take place and the heat is generated. Typically, the fuel will be low-enriched uranium contained in thousands of individual fuel pins. The core also contains structural components, the means to both moderate the neutrons and control the reaction, and the means to transfer the heat from the fuel to where it is required, outside the core.
Inside the core of a typical pressurized water reactor or boiling water reactor are fuel rods with a diameter of a large gel-type ink pen, each about 4 m long, which are grouped by the hundreds in bundles called "fuel assemblies". Inside each fuel rod, pellets of uranium, or more commonly uranium oxide, are stacked end to end. Also inside the core are control rods, filled with pellets of substances like boron or hafnium or cadmium that readily capture neutrons. When the control rods are lowered into the core, they absorb neutrons, which thus cannot take part in the chain reaction. Conversely, when the control rods are lifted out of the way, more neutrons strike the fissile uranium-235 (U-235) or plutonium-239 (Pu-239) nuclei in nearby fuel rods, and the chain reaction intensifies. The core shroud, also located inside of the reactor, directs the water flow to cool the nuclear reactions inside of the core. The heat of the fission reaction is removed by the water, which also acts to moderate the neutron reactions.
There are also graphite moderated reactors in use.
One type uses solid nuclear graphite for the neutron moderator and ordinary water for the coolant. See the Soviet-made RBMK nuclear-power reactor. This was the type of reactor involved in the Chernobyl disaster.
In the Advanced Gas-cooled Reactor, a British design, the core is made of a graphite neutron moderator where the fuel assemblies are located. Carbon dioxide gas acts as a coolant and it circulates through the core, removing heat.
Cette page est générée automatiquement et peut contenir des informations qui ne sont pas correctes, complètes, à jour ou pertinentes par rapport à votre recherche. Il en va de même pour toutes les autres pages de ce site. Veillez à vérifier les informations auprès des sources officielles de l'EPFL.
Explore la détection des neutrons dans les réacteurs nucléaires, en mettant l'accent sur les défis et les progrès dans les mesures de flux à haute résolution.
Explore les algorithmes de combustion, la discrétisation du temps, l'évolution du combustible LWR, la composition du combustible usé, les techniques de ravitaillement et le contrôle de l'acide borique dans les PWR.
In this course, one acquires an understanding of the basic neutronics interactions occurring in a nuclear fission reactor as well as the conditions for establishing and controlling a nuclear chain rea
This course is intended to understand the engineering design of nuclear power plants using the basic principles of reactor physics, fluid flow and heat transfer. This course includes the following: Re
The goal of the course is to provide the physics and technology basis for controlled fusion research, from the main elements of plasma physics to the reactor concepts.
Le réacteur modéré au graphite ou Graphite-moderated reactor est un réacteur nucléaire qui utilise le graphite comme modérateur, et habituellement de l'uranium naturel (non enrichi) comme combustible. Le premier réacteur nucléaire, la Chicago Pile-1, utilisait le graphite comme modérateur. Deux réacteurs modérés au graphite ont provoqué des catastrophes nucléaires : l'incendie de Windscale en 1957 en Angleterre et la catastrophe nucléaire de Tchernobyl en 1986 en RSS d'Ukraine, URSS (actuelle Ukraine).
A nuclear reactor core is the portion of a nuclear reactor containing the nuclear fuel components where the nuclear reactions take place and the heat is generated. Typically, the fuel will be low-enriched uranium contained in thousands of individual fuel pins. The core also contains structural components, the means to both moderate the neutrons and control the reaction, and the means to transfer the heat from the fuel to where it is required, outside the core.
Un poison neutronique (également appelé « absorbeur de neutrons » ou « poison nucléaire ») est une substance ayant une grande section d'absorption de neutrons, et qui a de ce fait un impact significatif dans le bilan neutronique d'un réacteur nucléaire. Dans les réacteurs nucléaires, l'absorption des neutrons a notamment un effet d'empoisonnement du réacteur. Cet empoisonnement est principalement dû à la capture de neutrons par des produits de fission de demi-vie courte dont le principal est le xénon 135 ou par des produits de fission de demi-vie plus longue ou stable comme le samarium 149 et le gadolinium 157.
In the last two decades, the use of OpenFOAM as a multi-physics library for nuclear applications has grown from a sporadic use for exploratory studies to a widespread application for the analysis of i
Nuclear reactors are inherently stochastic systems, in which neutronic and thermal-hydraulic parameters fluctuate continuously even during steady-state conditions. In addition, structural components v
EPFL2020
, ,
A porous medium-based representation of nuclear reactors and complex engineering systems more in general can significantly reduce simulation and modelling costs, while preserving a reasonable degree o