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The basic operation of the CANDU design is similar to other nuclear reactors. Fission reactions in the reactor core heat pressurized water in a primary cooling loop . A heat exchanger , also known as a steam generator , transfers the heat to a secondary cooling loop , which powers a steam turbine with an electric generator attached to it (for a ...
The Advanced CANDU reactor (ACR), or ACR-1000, was a proposed Generation III+ nuclear reactor design, developed by Atomic Energy of Canada Limited (AECL). It combined features of the existing CANDU pressurised heavy water reactors (PHWR) with features of light-water cooled pressurized water reactors (PWR).
Candu Energy Inc. is a Canadian wholly owned subsidiary of Montreal-based AtkinsRéalis (formerly SNC-Lavalin Inc.), specializing in the design and supply of nuclear reactors, as well as nuclear reactor products and services. Candu Energy Inc. was created in 2011 when parent company SNC-Lavalin purchased the commercial reactor division of ...
The first CANDU was a demonstration unit, the Nuclear Power Demonstrator (NPD). In 1958, before NPD was complete, AECL formed the Nuclear Power Plant Division at Ontario Hydro’s A.W. Manby Service Centre in Toronto to manage the construction of a full-scale prototype for future CANDU commercial power plants.
The Advanced CANDU Reactor is a hybrid CANDU design that retains the heavy water moderator but replaces the heavy water coolant with conventional light water coolant, significantly reducing heavy water costs compared to traditional CANDU designs but losing the characteristic CANDU capability of using unenriched natural uranium as fuel. BARC ...
This is a thermal-neutron reactor design, the newest of which are the Advanced Boiling Water Reactor and the Economic Simplified Boiling Water Reactor. The CANDU Qinshan Nuclear Power Plant. Pressurized Heavy Water Reactor (PHWR) [moderator: high-pressure heavy water; coolant: high-pressure heavy water]
Atomic Energy of Canada Limited (AECL) is a Canadian Crown corporation and the largest nuclear science and technology laboratory in Canada. AECL developed the CANDU reactor technology starting in the 1950s, and in October 2011 licensed this technology to Candu Energy.
In nuclear engineering, the void coefficient (more properly called void coefficient of reactivity) is a number that can be used to estimate how much the reactivity of a nuclear reactor changes as voids (typically steam bubbles) form in the reactor moderator or coolant. Net reactivity in a reactor depends on several factors, one of which is the ...