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CANadian Deuterium Uranium reactor

The Canadian Deuterium Uranium reactor fissions with natural uranium, hence, no dependence on national or international fuel enrichment facilities that are needed to enrich uranium to about 3% U-235 to achieve criticality with light water moderation. [Pg.404]

The vast majority (80%) of the reactors mentioned are light-water-moderated reactors (LWR). The LWR subdivide in 60% PWR and 20% BWR. The remaining 20% of the reactors are divided among CANadian Deuterium Uranium reactor (CANDU), Reaktor Bolshoi Moshchnosti Kanalny (RBMK), large power channel reactor, gas-cooled reactor (GCR), advanced gas-cooled reactor (AGR), and fast breeder reactor (FBR). [Pg.2640]

CANDU Canadian deuterium-uranium (reactor) MT metric ton... [Pg.8]

Canadian Deuterium-Uranium Reactor (CANDU). The CANDU reactor is interesting because it can mn continuously and be fueled online. With a capacity factor near 100%, the CANDU bums plutonium the quickest. Online fueling would also be very useful for putting the entire inventory through one reactor rapidly to self-protect the fuel. Because plutonium provides excess core reactivity, the core could be cooled and moderated with light water instead of heavy water. The large core also allows low power densities. However, this modified CANDU concept could have positive temperature coefficients of reactivity. Lack of experience with this concept is the main reason that it has not been studied further. [Pg.119]

The GANDU Reactors. The Canadian deuterium uranium (CANDU) reactors are unique among power reactors in several respects. Heavy water is used as moderator natural uranium having 235u... [Pg.219]

Deuterium, 8 456—485 13 759. See also Canadian Deuterium Uranium (CANDU) reactors analytical methods, 8 467-468 economic aspects, 8 467 health and safety factors, 8 461-462 physical properties, 8 457-462, 459t production of heavy water, 8 459t, 462-467... [Pg.257]

The initial surface composition of boiler tubing, prior to its installation will have an important impact on the amount and type of activated corrosion products in an aqueous reactor coolant. Consequently, the type of thermal pre-treatment the tubing undergoes, for example, for mechanical stress release,will affect the surface oxide film, and ultimately, the corrosion behavior. This particular work has been directed toward characterization of surface oxide films which form on Inconel 600 (nominal composition 77% Ni, 16% Cr, 7% Fe, — a tradename of Inco Metals Ltd., Toronto Canada) and Incoloy 800 (nominal composition 31% Ni, 19% Cr, 48% Fe 2% other, — a tradename of Inco Metals Ltd., Toronto, Canada) heated to temperatures of 500-600°C for periods of up to 1 minute in flowing argon. These are conditions equivalent to those experi enced by CANDU(CANadian Deuterium Uranium)ractor boiler hairpins during in situ stress relief. [Pg.359]

Five existing reactor types were selected for consideration to cover a broad range of possible neutron spectral characteristics. In alphabetical order, the types examined are a boiling water reactor (BWR), a Canadian deuterium-uranium (CANDU) reactor, a high-temperature gas-cooled reactor (HTGR), a liquid metal reactor (LMR), and a PWR. [Pg.29]

Although LEO had been dropped from the programme, work on various forms of water reactor did not stop. A variety of studies were continued into various other esoteric forms of water-cooled reactor, for example, the steam cooled heavy water reactor (SCHWR) or the steam generating heavy water reactor (SGHWR). Meanwhile, the Canadians continued to build on their wartime work on heavy water, and had produced a design for a reactor using natural uranium and heavy water. This design was known as the CANDU (Canada deuterium uranium) reactor. [Pg.258]

Other newer designs include the advanced, gas-cooled reactor (AGR), Canadian deuterium reactor (CANDUR), sodium-cooled reactor (SCR), sodium-heated reactor (SHR), and fast breeder reactor (FBR). These reactors employ either natural or enriched uranium fuels that may be modified in some way (e.g., graphite-moderated fuels). [Pg.63]

CAN DU A type of Canadian heavy-water-moderated pressure tube natural uranium reactor. The name is derived from Canadian, deuterium (i.e. heavy water) and uranium fuel. [Pg.50]

CANDU CANada Deuterium f/ranium. It is a Canadian-designed power reactor of PHWR type (Pressurized Heavy Water Reactor) that uses heavy water (deuterium oxide) for moderator and coolant, and natural uranium for fuel. [Pg.127]


See other pages where CANadian Deuterium Uranium reactor is mentioned: [Pg.268]    [Pg.11]    [Pg.394]    [Pg.690]    [Pg.268]    [Pg.11]    [Pg.394]    [Pg.690]    [Pg.135]    [Pg.404]    [Pg.563]    [Pg.1]    [Pg.448]    [Pg.32]    [Pg.101]    [Pg.1114]    [Pg.665]    [Pg.101]    [Pg.313]    [Pg.2385]    [Pg.2639]    [Pg.231]    [Pg.564]   
See also in sourсe #XX -- [ Pg.268 ]




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