The CANDU is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide moderator and its use of uranium fuel. CANDU reactors were first developed in the late 1950s and 1960s by a partnership between Atomic Energy of Canada Limited (AECL), the Hydro-Electric Power Commission of Ontario, Canadian General Electric, and other companies.
Atomic Energy of Canada Limited (AECL) is a Canadian federal Crown corporation and Canada's largest nuclear science and technology laboratory. AECL developed the CANDU reactor technology starting in the 1950s, and in October 2011 licensed this technology to Candu Energy.
Bruce Nuclear Generating Station is a nuclear power station located on the eastern shore of Lake Huron in Ontario, Canada. It occupies 932 ha of land. The facility derives its name from Bruce Township, the local municipality when the plant was constructed, now Kincardine due to amalgamation. With eight CANDU pressurized heavy-water reactors, it was the world's largest fully operational nuclear generating station by total reactor count and the number of currently operational reactors until 2016, when it was exceeded in nameplate capacity by South Korea's Kori Nuclear Power Plant. The station is the largest employer in Bruce County, with over 4000 workers.
Gentilly Nuclear Generating Station is a former nuclear power station located on the south shore of the St. Lawrence River in Bécancour, Quebec, 100 km north east of Montreal. The site contained two nuclear reactors; Gentilly-1, a 250 MW CANDU-BWR prototype, was marred by technical problems and shut down in 1977, and Gentilly-2, a 675-MW CANDU-6 reactor operated commercially by the government-owned public utility Hydro-Québec between 1983 and 2012. These were the only power generating nuclear reactors in Quebec.
In nuclear engineering, the void coefficient is a number that can be used to estimate how much the reactivity of a nuclear reactor changes as voids form in the reactor moderator or coolant. Net reactivity in a reactor is the sum total of all these contributions, of which the void coefficient is but one. Reactors in which either the moderator or the coolant is a liquid typically will have a void coefficient value that is either negative or positive. Reactors in which neither the moderator nor the coolant is a liquid will have a void coefficient value equal to zero. It is unclear how the definition of 'void' coefficient applies to reactors in which the moderator/coolant is neither liquid nor gas.
The ZEEP reactor was a nuclear reactor built at the Chalk River Laboratories near Chalk River, Ontario, Canada. ZEEP first went critical at 15:45 on September 5, 1945. ZEEP was the first operational nuclear reactor outside the United States.
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). From CANDU, it took the heavy water moderator, which gave the design an improved neutron economy that allowed it to burn a variety of fuels. It replaced the heavy water cooling loop with one containing conventional light water, reducing costs. The name refers to its design power in the 1,000 MWe class, with the baseline around 1,200 MWe.
The Steam Generating Heavy Water Reactor (SGHWR) is a United Kingdom design for commercial nuclear reactors. It uses heavy water as the neutron moderator and normal "light" water as the coolant. The coolant boils in the reactor, like a boiling water reactor, and drives the power-extraction steam turbines.
Nuclear Power Demonstration was the first Canadian nuclear power reactor, and the prototype for the CANDU reactor design. Built by Canadian General Electric, in partnership with Atomic Energy of Canada Limited (AECL), Ontario Hydro and the US Atomic Energy Commission (AEC), it consisted of a single 22 MWe pressurized heavy water reactor (PHWR) unit located in Rolphton, Ontario, not far from AECL's Chalk River Laboratories. NPD was owned by AECL and operated by Ontario Hydro.
The Douglas Point Nuclear Generating Station was Canada’s first full-scale nuclear power plant and the second CANDU pressurised heavy water reactor. Its success was a major milestone and marked Canada's entry into the global nuclear power scene. The same site was later used for the Bruce Nuclear Generating Station, which was built just to the south of Douglas Point.
Nuclear power in Canada is provided by 19 commercial reactors with a net capacity of 13.5 gigawatt (GW), producing a total of 95.6 terawatt-hours (TWh) of electricity, which accounted for 16.6% of the country's total electric energy generation in 2015. All but one of these reactors are located in Ontario, where they produced 61% of the province's electricity in 2019. Seven smaller reactors are used for research and to produce radiopharmaceuticals for use in nuclear medicine.
The Whiteshell Reactor No. 1, or WR-1, was a Canadian research reactor located at AECL's Whiteshell Laboratories (WNRL) in Manitoba. Originally known as Organic-Cooled Deuterium-Reactor Experiment (OCDRE), it was built to test the concept of a CANDU-type reactor that replaced the heavy water coolant with an oil substance. This had a number of potential advantages in terms of cost and efficiency.
The Nuclear Power Plant in Cernavodă is the only nuclear power plant in Romania. It produces around 20% of the country's electricity. It uses CANDU reactor technology from AECL, using heavy water produced at Drobeta-Turnu Severin as its neutron moderator and as its coolant agent. The Danube water is not used for cooling of the active zone.
CANFLEX; the name is derived from its function: CANDU FLEXible fuelling, is an advanced fuel bundle design developed by Atomic Energy of Canada Ltd. (AECL), along with the Korean Atomic Energy Research Institute (KAERI) for use in CANDU design nuclear reactors. The designers claim that it will deliver many benefits to current and future CANDU reactors-using natural uranium or other advanced nuclear fuel cycles. These include greater operating and safety margins, extended plant life, better economics and increased power.
The Qinshan Nuclear Power Plant (秦山核电站) is a multi-unit nuclear power plant in Qinshan Town, Haiyan County, in Jiaxing, Zhejiang province, China.
Nuclear industry in Canada is an active business and research sector, producing about 15% of its electricity in nuclear power plants of domestic design. Canada is the world's largest exporter of uranium, and has the world's second largest proven reserves. Canada also exports nuclear technology within the terms of the Nuclear Non-proliferation Treaty, to which it is a signatory, and is the world's largest producer of radioactive medical isotopes.
In Argentina, about 10% of the electricity comes from 3 operational nuclear reactors: The Embalse Nuclear Power Station, a CANDU reactor, and the Atucha 1 plant in 1974, a PHWR German design. In 2001, the plant was modified to burn Slightly Enriched Uranium, making it the first PHWR reactor to burn that fuel worldwide. Atucha was originally planned to be a complex with various reactors. Atucha 2 began to produce energy on June 3, 2014, and it is expected to produce 745MWh. Plans for Atucha III, a third reactor in the Atucha complex, have been announced.
Candu Energy Inc. is a Canadian wholly owned subsidiary of Montreal-based 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 Atomic Energy of Canada Limited (AECL), along with the development and marketing rights to CANDU reactor technology.
The IPHWR-700 is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. It is a Generation III reactor developed from earlier CANDU based 220 MW and 540 MW designs. It can generate 700 MW of electricity. Currently there are 6 units under construction and 10 more units planned, at a cost of INR 1.05 trillion.
The IPHWR is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan. The design was later expanded into 540 MW and 700 MW designs. Currently there are 17 units of various types operational at various locations in India.
