187:) are stored inside isolated channels located directly above the reactor vessel (calandria) and are controlled via a triple-channel logic circuit. When any 2 of the 3 circuit paths are activated (due to sensing the need for emergency reactor trip), the direct current-controlled clutches that keep each control-rod in the storage position are de-energized. The result is that each control-rod is inserted into the calandria, and the reactor heat output is reduced by 90% within 2 seconds.
146:(LEU) fuel. This allows the reactor core to be built much more compactly, roughly half that of a CANDU of the same power. Additionally, it replaces the heavy water coolant in the high-pressure section of the calandria with conventional "light" water. This greatly reduces the amount of heavy water needed, and the cost of the primary coolant loop. Heavy water remains in the low-pressure section of the calandria, where it is essentially static and used only as a moderator.
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299:(RFP) for the Darlington B installation. Ultimately, AECL was the only company to place a formal bid, with a two-reactor ACR-1000 plant. The bids required that all contingencies for time and budget overruns be considered in the plans. The resulting bid was $ 26 billion for a total of 2,400 MWe, or over $ 10,800 per kilowatt. This was three times what had been expected, and called "shockingly high". As this was the only bid, the
344:
205:) solution, a neutron-absorbing liquid that shuts down the nuclear chain reaction, is stored inside channels that feed into horizontal nozzle assemblies. Each nozzle has an electronically controlled valve, all of which are controlled via a triple-channel logic circuit. When any 2 of the 3 circuit paths are activated (due to sensing the need for emergency reactor trip), each of these valves are opened and Gd(NO
314:(CNNC) to support sales and construction of the existing CANDU designs. Among these was a plan to use their two CANDU-6 reactors in a recycling scheme under the name Advanced Fuel CANDU Reactor (AFCR). However, these plans did not proceed. SNC and CNNC subsequently announced collaboration on a Heavy Water Reactor, also based on legacy CANDU technology, and unrelated to the
291:
AECL was marketing the ACR-1000 as part of the UK's
Generic Design Process but pulled out in April 2008. CEO Hugh MacDiarmid is quoted as stating, "We believe very strongly that our best course of action to ensure the ACR-1000 is successful in the global market place is to focus first and foremost on
253:
of greater than 93%. This is achieved by a three-year planned outage frequency, with a 21-day planned outage duration and 1.5% per year forced outage. Quadrant separation allows flexibility for on-line maintenance and outage management. A high degree of safety system testing automation also reduces
125:
However, the use of natural uranium also meant the core was much less dense compared to other designs, and much larger overall. It was expected this additional cost would be offset by lower capital costs on other items, as well as lower operational costs. The key trade-off was the cost of the fuel,
129:
In practice, these advantages did not work out. The high expected fuel costs never came to be; when reactor construction stalled at around 200 units worldwide, instead of the expected thousands, fuel costs remained steady as there was ample enrichment capability for the amount of fuel being used.
76:
The ACR-1000 was introduced as a lower-priced option compared to a larger version of the baseline CANDU which was being designed, the CANDU 9. ACR was slightly larger but less expensive to build and run. The downside was that it did not have the flexibility of fuels that the original CANDU design
117:
Further, the design used both pressurized and unpressurized sections, the latter known as a "calandria", which it was believed would lower construction costs compared to designs that used highly pressurized cores. In contrast to typical light-water designs, CANDU did not require a single large
176:
The ACR-1000 design currently calls for a variety of safety systems, most of which are evolutionary derivatives of the systems utilized on the CANDU 6 reactor design. Each ACR requires both SDS1 & SDS2 to be online and fully operational before they will operate at any power level.
229:
The EPS system is designed to provide each ACR unit with the required electrical power needed to perform all safety functions under both operating & accident conditions. It contains seismically qualified, redundant standby generators, batteries and distribution switchgear.
72:
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.
113:
for fuel, eliminating the need for enrichment. At the time, it was believed there would be hundreds and perhaps thousands of nuclear reactors in operation by the 1980s, and in that case the cost of enrichment would become considerable.
240:
O) required to perform all safety system-related functions under both operating & accident conditions. All safety-related portions of the system are seismically qualified and contain redundant divisions.
84:, but this project was canceled in 2009 when the price was estimated to be three times what the government was budgeting. With no other sales prospects, in 2011 the AECL reactor design division was sold to
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solution is injected through the nozzles to mix with the heavy-water moderator liquid in the reactor vessel (calandria). The result is that the reactor heat output is reduced by 90% within 2 seconds.
542:
288:
Canada and SNC-Lavalin
Nuclear, which proposed using a 1085 MWe ACR-1000. Nothing further came of this bid. It was later replaced by a mid-2010 bid by Areva, a bid that also lapsed.
471:
223:(LOCA). The RWS can also provide emergency water (via gravity-feed) to the steam generators, moderator system, shield cooling system or the heat transport system of any ACR.
584:"SNC-Lavalin awarded contract from China National Nuclear Power for pre-project work for the proposed 2-unit Advanced Heavy Water Reactor new build project in China"
164:
The fuel bundle is a variant of the 43-element CANFLEX design (CANFLEX-ACR). The use of LEU fuel with a neutron absorbing centre element allows the reduction of
219:
The RWS consists of a water tank located at a high elevation within the reactor building. This provides water for use in cooling an ACR that has suffered a
153:
devices are located within the low-pressure moderator. The ACR also incorporates characteristics of the CANDU design, including on-power refueling with the
130:
This left CANDU in the unexpected position of selling itself primarily on the lack of need for enrichment and the possibility that this presented a lower
118:
pressure vessel, which was among the more complex parts of other designs. This design also allowed it to be refuelled while it was running, improving the
77:
offered, and would no longer run on pure unenriched uranium. This was a small price to pay given the low cost of enrichment services and fuel in general.
109:
and the coolant for the primary cooling loop. It was believed that this design would result in lower overall operating costs due to its ability to use
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AECL bid the ACR-1000 on several proposals around the world but won no contests. The last serious proposal was for a two-reactor expansion of the
804:
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SDS1 is designed to rapidly and automatically terminate reactor operation. Neutron-absorbing rods (control rods that shut down the nuclear
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considered ACR in 2007 for deployment in
Western Canada, both for power generation, or for steam generation to be used in processing
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in an era when enriched uranium fuel was limited and expensive and its price was expected to rise considerably by the 1980s.
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lifetime; small reactivity holdup; two fast, independent, safety shutdown systems; and an emergency core cooling system.
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to a nominally small, negative value. It also results in higher burnup operation than traditional CANDU designs.
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In 2008, the province of New
Brunswick accepted a proposal for a feasibility study for an ACR-1000 at
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In 2011, with no sales prospects remaining, the
Canadian government sold AECL's reactor division to
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SDS2 is also designed to rapidly and automatically terminate reactor operation.
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to provide services to the existing CANDU fleet. Development of the ACR ended.
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ACR addresses the high capital costs of the CANDU design primarily by using
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269:. In 2011, Bruce Power decided not to move forward with this project.
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276:. This led to a formal bid by Team Candu, consisting of AECL,
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543:"SNC-Lavalin strikes deal to build nuclear reactors in China"
472:"Bruce Power will not proceed with nuclear option in Alberta"
376:
54:
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381:
819:
604:
360:- a prototype heavy water reactor fueled with ~2% U235
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503:"Canada's AECL pulls out of UK nuclear reactor study"
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453:CANDU 6 – Safety Systems – Special Safety Systems
303:decided to cancel the expansion project in 2009.
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310:. In 2014, SNC announced a partnership with the
295:The ACR-1000 was submitted as part of Ontario's
27:Canadian third generation nuclear reactor design
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236:The CWS provides all necessary light water (H
68:moderator, which gave the design an improved
53:(AECL). It combined features of the existing
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60:(PHWR) with features of light-water cooled
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122:, a key metric in overall performance.
14:
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936:Nuclear Waste Management Organization
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301:Ministry of Energy and Infrastructure
82:Darlington Nuclear Generating Station
425:
227:Emergency power supply system (EPS):
562:Hore-Lacy, Ian (11 November 2014).
244:
166:coolant void reactivity coefficient
24:
977:Canadian Nuclear Safety Commission
600:Canadian Nuclear Safety Commission
312:China National Nuclear Corporation
25:
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593:
564:"The AFCR and China's fuel cycle"
171:
1024:
1023:
541:Marotte, Bertrand (2016-09-22).
520:Hamilton, Tyler (14 July 2009).
501:Fineren, Daniel (7 April 2008).
342:
328:
191:Safety Shutdown System 2 (SDS2):
181:Safety Shutdown System 1 (SDS1):
58:pressurised heavy water reactors
1050:Atomic Energy of Canada Limited
1013:Anti-nuclear movement in Canada
957:Atomic Energy of Canada Limited
522:"$ 26B cost killed nuclear bid"
358:Carolinas–Virginia Tube Reactor
292:establishing it here at home."
249:The ACR has a planned lifetime
101:The original CANDU design used
64:(PWR). From CANDU, it took the
51:Atomic Energy of Canada Limited
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149:The reactivity regulating and
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972:Canadian Nuclear Association
662:Electricity sector in Canada
610:Canadian Nuclear Association
318:being developed in India.
316:Advanced Heavy Water Reactor
7:
1055:Nuclear power reactor types
919:McArthur River uranium mine
733:Nuclear Power Demonstration
458:September 27, 2007, at the
408:"CANDU Reactors – ACR-1000"
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234:Cooling water system (CWS):
217:Reserve water system (RWS):
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667:Nuclear industry in Canada
62:pressurized water reactors
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440:World Nuclear Association
436:"Nuclear Power in Canada"
350:Nuclear technology portal
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992:Ontario Power Generation
987:Natural Resources Canada
941:Deep Geologic Repository
904:Uranium mining in Canada
870:Chalk River Laboratories
605:Canadian Nuclear Society
221:loss of coolant accident
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880:Whiteshell Laboratories
657:Energy policy of Canada
646:Nuclear power in Canada
788:and prototype reactors
786:Research, experimental
363:Other Gen III designs
144:low-enrichment uranium
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32:Advanced CANDU reactor
18:Advanced CANDU Reactor
132:nuclear proliferation
49:design, developed by
758:Power plant reactors
297:request for proposal
286:Babcock & Wilcox
875:McMaster University
863:Research locations
569:World Nuclear News
548:The Globe and Mail
195:Gadolinium nitrate
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909:McClean Lake mine
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738:Pickering (A2/A3)
442:. September 2016.
107:neutron moderator
42:, was a proposed
16:(Redirected from
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476:Bruce Power
308:SNC-Lavalin
263:Bruce Power
258:Abandonment
103:heavy water
86:SNC-Lavalin
66:heavy water
1044:Categories
895:Fuel cycle
697:Darlington
486:11 October
418:2013-03-24
395:References
897:locations
702:Pickering
278:GE Canada
267:oil sands
1030:Category
840:SLOWPOKE
728:Gentilly
456:Archived
322:See also
284:Canada,
40:ACR-1000
507:Reuters
387:US-APWR
282:Hitachi
155:CANFLEX
967:Cameco
835:STOR-M
716:Closed
685:Active
372:AP1000
254:cost.
197:(Gd(NO
151:safety
134:risk.
92:Design
38:), or
845:ZED-2
805:MAPLE
777:SGHWR
692:Bruce
377:ESBWR
97:CANDU
55:CANDU
850:ZEEP
800:IMSR
765:PHWR
488:2013
382:ABWR
30:The
830:PTR
825:NRU
820:NRX
815:MTF
810:MNR
367:EPR
138:ACR
36:ACR
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