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Supercritical-Water-cooled Reactor

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Supercritical-Water-cooled Reactor
NameSupercritical-Water-cooled Reactor
ConceptNuclear reactor type
DeveloperVarious national programs
StatusExperimental / Proposed / Developmental
FuelUranium, Mixed oxide
CoolantSupercritical water
ModeratorLight water / Heavy water / None
OutputElectricity

Supercritical-Water-cooled Reactor The supercritical-water-cooled reactor is an advanced nuclear reactor concept that uses water above its thermodynamic critical point as the primary coolant to achieve higher thermal efficiency and simplified power cycles. Early research programs and design studies have been pursued by national laboratories, industrial consortia, and research reactors associated with major institutions, aiming to apply lessons from light-water reactor development to higher-temperature supercritical steam cycles.

Overview

Supercritical-water-cooled Reactor designs build on developments from Boiling water reactor, Pressurized water reactor, Magnox, Advanced Gas-cooled Reactor, and concepts from Sodium-cooled fast reactor, Lead-cooled fast reactor, and High-temperature gas-cooled reactor communities. Programmes in Japan, China, Canada, Germany, United States Department of Energy, Rosatom, and collaborations with institutions such as Argonne National Laboratory, Japan Atomic Energy Agency, China National Nuclear Corporation, and AECL have driven research. Design goals reference thermodynamic cycles like the Rankine cycle and technologies applied in projects such as Hinkley Point C, Kashiwazaki-Kariwa Nuclear Power Plant, and partnerships with manufacturers including Westinghouse Electric Company, Toshiba, and Siemens. Policy and industrial context involve agencies like the International Atomic Energy Agency and standards organizations such as American Society of Mechanical Engineers.

Design and Technology

Design proposals typically employ supercritical water at pressures above 22.1 MPa and temperatures up to or exceeding 500 °C, integrating high-pressure components analogous to those in Advanced boiling water reactor proposals and lessons from European Pressurized Reactor and AP1000. Core and pressure-vessel arrangements draw engineering practice from Babcock & Wilcox heritage and vessel technologies tested in facilities like Oak Ridge National Laboratory and Institut Laue–Langevin. Turbine and plant layout leverage high-efficiency steam turbine designs used at sites such as Drax Power Station and systems by companies like General Electric and Mitsubishi Heavy Industries. Materials research connects to programs at Sandia National Laboratories, Los Alamos National Laboratory, Cranfield University, and industrial metallurgy groups in Sweden and France working on corrosion-resistant alloys and cladding similar to efforts for Zirconium alloys and alternative claddings studied in the context of Mixed oxide fuel use.

Fuel and Core Configurations

Fuel options explored include enriched uranium dioxide fuel assemblies comparable to those used at Pickering Nuclear Generating Station and Fukushima Daiichi Nuclear Power Plant operational histories, and mixed oxide fuels developed in programs like those at Sellafield and by BNFL. Core geometries reference lattice concepts from CANDU and rod-bundle arrangements from Koeberg Nuclear Power Station, with moderator choices spanning light water, heavy water as in Gentilly-2, or fast-spectrum, reflecting research themes seen in Integral Fast Reactor studies. Reload strategies and burnup expectations look to standards from Nuclear Energy Agency datasets and experience at facilities such as Olkiluoto Nuclear Power Plant and VVER reactors operated by Rosatom affiliates.

Safety Features and Systems

Safety approaches rely on passive and active systems influenced by post-accident analyses from Chernobyl disaster, Three Mile Island accident, and Fukushima Daiichi nuclear disaster reviews, with emphasis on inherent safety characteristics and defense-in-depth frameworks discussed by Nuclear Regulatory Commission and Office for Nuclear Regulation. Containment, emergency core cooling analogues, and passive heat removal draw on lessons from EPR and AP1000 designs, while probabilistic risk assessments reference methodologies developed by International Atomic Energy Agency and Organisation for Economic Co-operation and Development. Materials behavior under supercritical conditions informs accident-tolerant fuel research pursued at Idaho National Laboratory and joint international test reactors.

Operational History and Deployment

No commercial Supercritical-Water-cooled Reactor has achieved wide commercial operation; experimental and demonstration programs were undertaken by national projects in Japan and China with test loops and prototype studies at facilities connected to Japan Atomic Energy Agency and Tsinghua University. International collaborations have included exchanges with European Commission research frameworks and bilateral cooperation between agencies such as US Department of Energy and Ministry of Economy, Trade and Industry (Japan). Deployment pathways reference licensing practices used for Flamanville and regulatory precedents set by Nuclear Regulatory Commission rulings and national licensing bodies, as seen in the phased approaches applied at Olkiluoto 3 and Hinkley Point C.

Economic and Regulatory Considerations

Economic assessments compare levelized costs with advanced designs like Small modular reactor proposals, Generation IV concepts, and fossil gas combined-cycle plants at assets such as Sakhalin-II and power market experiences in California, Texas, and Germany. Financing and industrial supply chains consider major vendors including Rosatom, Westinghouse, Mitsubishi Heavy Industries, and consortium models used for Flamanville and Hinkley Point C. Regulatory frameworks implicate international review by International Atomic Energy Agency missions and national regulators such as Nuclear Regulatory Commission and Office for Nuclear Regulation, which guide certification, safety case development, and environmental assessment processes similar to those applied for VVER and AP1000 projects. Market adoption depends on policy drivers exemplified by energy transitions in United Kingdom, France, China, and Japan and on competition with renewable deployments and grid integration strategies observed in Denmark and Spain.

Category:Nuclear reactors