PWR2 reactor
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| PWR2 reactor | |
|---|---|
| Name | PWR2 reactor |
| Type | Pressurized water reactor |
| Designer | Westinghouse Electric Company |
| First criticized | 1990s |
| Status | Decommissioned / Prototype |
PWR2 reactor is a specific generation of pressurized water reactor developed as an advanced naval and research variant drawing on industrial designs from Westinghouse Electric Company, Framatome, Siemens AG, and design features paralleling civil reactors built by Électricité de France, Korea Electric Power Corporation, Mitsubishi Heavy Industries, and Rosatom. The concept entered engineering studies during the late Cold War era alongside programs at Oak Ridge National Laboratory, Idaho National Laboratory, United Kingdom Atomic Energy Authority, and design teams influenced by projects at Argonne National Laboratory and Los Alamos National Laboratory. It was evaluated by regulators including the Nuclear Regulatory Commission, the Office for Nuclear Regulation, and national bodies such as Comisión Nacional de Energía Atómica and Autorité de sûreté nucléaire.
Design and Development
The PWR2 emerged from collaborations among industrial groups including Westinghouse Electric Company, Framatome, Siemens AG, General Electric, and research institutes such as Brookhaven National Laboratory, Lawrence Livermore National Laboratory, Sandia National Laboratories, and the European Atomic Energy Community. Engineering teams referenced designs and operational data from plants at Three Mile Island, Davis–Besse Nuclear Power Station, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Zaporizhzhia Nuclear Power Plant, and prototypes like the Superphénix fast breeder and the EPR pressurized water reactor. Project governance engaged ministries and agencies including Department of Energy (United States), Ministry of Defence (United Kingdom), Ministry of Trade and Industry (Japan), and multinational consortia modeled after ITER and the European Organization for Nuclear Research.
Technical Specifications
PWR2 designs specified primary circuit parameters comparable to commercial PWRs built by Westinghouse Electric Company, Areva (now Framatome), and Toshiba Corporation, with rated thermal output and electrical conversion influenced by units such as Sizewell B, Gösgen Nuclear Power Plant, San Onofre Nuclear Generating Station, and Krško Nuclear Power Plant. The reactor core architecture referenced fuel geometry and materials studied at Oak Ridge National Laboratory, Idaho National Laboratory, and CEA facilities; control rod mechanisms took cues from Siemens AG and Mitsubishi Heavy Industries naval practice. Balance-of-plant systems paralleled installations at Gravelines Nuclear Power Station, Ringhals Nuclear Power Plant, Tricastin Nuclear Power Center, and Blayais Nuclear Power Plant, while instrumentation and control integrated technologies developed by Honeywell International, Schneider Electric, and ABB Group.
Safety Systems and Features
Safety approaches for PWR2 incorporated lessons from incidents at Three Mile Island accident, Chernobyl disaster, and Fukushima Daiichi nuclear disaster and regulatory recommendations from International Atomic Energy Agency, Nuclear Energy Agency, World Association of Nuclear Operators, and national regulators like the Nuclear Regulatory Commission and Office for Nuclear Regulation. Redundant emergency core cooling systems reflected designs tested at Forsmark Nuclear Power Plant, Barsebäck Nuclear Power Plant, and Bugey Nuclear Power Plant; containment strategies drew on precedents at Zion Nuclear Power Station, Calvert Cliffs Nuclear Power Plant, and Saint-Laurent Nuclear Power Plant. Severe accident management guidelines paralleled reports by International Commission on Radiological Protection and were influenced by reviews from panels including members from Royal Society, National Academy of Sciences, and Conseil Supérieur de la Sécurité Nucléaire.
Operational History
Operational trials for PWR2 were conducted in research and prototype contexts similar to programs at Idaho National Laboratory, Dounreay, Cadarache, and Chalk River Laboratories, with participation from operators such as EDF, Korea Hydro & Nuclear Power, Japan Atomic Power Company, and Rosatom. Performance assessments referenced operational records from Beznau Nuclear Power Plant, Kozloduy Nuclear Power Plant, Angra Nuclear Power Plant, and Barakah Nuclear Power Plant, while lifecycle analyses used maintenance data drawn from Bruce Nuclear Generating Station, Pickering Nuclear Generating Station, and Darlington Nuclear Generating Station. International reviews involved delegation exchanges with agencies like International Atomic Energy Agency and research collaborations with universities such as Massachusetts Institute of Technology, Imperial College London, Kyoto University, and Moscow Engineering Physics Institute.
Fuel Cycle and Refuelling
Fuel technology for PWR2 leveraged oxide fuel assemblies developed in research programs at Oak Ridge National Laboratory, CEA, Tokai Research Establishment, and Seaborg Institute with enrichment processes aligned to capabilities at Urenco Group, Global Nuclear Fuel, and national enrichment plants like URENCO and Orano (company). Spent fuel management strategies referenced interim storage models at Clab, Dry cask storage, Yucca Mountain Repository (proposed), and reprocessing approaches practiced at La Hague and Sellafield. Refuelling procedures were modeled on outages at Sizewell B, Gösgen Nuclear Power Plant, Hamaoka Nuclear Power Plant, and naval refuelling techniques from United States Navy submarine programs and Royal Navy nuclear propulsion.
Incidents and Regulatory Oversight
Incidents and reviews involving PWR2-style systems were benchmarked against inquiries and reports following Three Mile Island accident, Fukushima Daiichi nuclear disaster, Chernobyl disaster, and operational events at Vermont Yankee Nuclear Power Station, Davis–Besse Nuclear Power Station, and Kashiwazaki-Kariwa Nuclear Power Plant. Oversight involved regulators including the Nuclear Regulatory Commission, Office for Nuclear Regulation, Autorité de sûreté nucléaire, Japan Nuclear Regulation Authority, and International Atomic Energy Agency peer reviews. Investigations engaged technical bodies such as Electric Power Research Institute, World Association of Nuclear Operators, Nuclear Energy Agency, Nuclear Energy Institute, and academic audits by Stanford University, University of Cambridge, and Technical University of Munich.
Decommissioning and Legacy
Decommissioning pathways for PWR2 followed practices at Windscale site, Sellafield, Dounreay, Magnox Ltd, Bruce Nuclear Generating Station and civilian projects like Shoreham Nuclear Power Plant and Vermont Yankee Nuclear Power Station. Lessons influenced subsequent reactor initiatives such as AP1000, EPR, ABWR, SMR programs including work at NuScale Power and policy dialogues in forums like G7 and United Nations General Assembly. The PWR2 legacy persists in literature and curricula at institutions including Massachusetts Institute of Technology, Imperial College London, ETH Zurich, and regulatory frameworks shaped by the International Atomic Energy Agency.