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| Prototype Fast Reactor | |
|---|---|
| Name | Prototype Fast Reactor |
| Location | Dounreay, Caithness |
| Country | United Kingdom |
| Operator | United Kingdom Atomic Energy Authority |
| Status | decommissioned |
| Construction started | 1957 |
| Commissioned | 1974 |
| Decommissioned | 1994 |
| Reactor type | sodium-cooled fast reactor |
| Electrical capacity | 250 MW |
| Thermal capacity | 560 MW |
Prototype Fast Reactor The Prototype Fast Reactor was a sodium-cooled fast breeder reactor constructed at Dounreay in Caithness, Scotland by the United Kingdom Atomic Energy Authority as part of the UK civil nuclear programme and the broader international development of fast reactor technology during the Cold War. It served as a technology demonstrator linking research from establishments such as Harwell and Winfrith to industrial partners including Rolls-Royce, National Nuclear Corporation, and the Atomic Energy of Canada Limited collaborations. The project intersected with policy debates in the Ministry of Defence, energy strategy discussions in the Department of Energy (United Kingdom), and international cooperation under institutions like the International Atomic Energy Agency and the OECD Nuclear Energy Agency.
The Prototype Fast Reactor was conceived in the context of early post-war programs led by figures at Culham Laboratory, Winfrith Atomic Energy Establishment, and the United Kingdom Atomic Energy Authority to pursue fast neutron systems similar to efforts at BN-350, Monju, and the Phénix reactor. Strategic influences included lessons from wartime projects in Los Alamos National Laboratory and industrial reactor development at Westinghouse Electric Company, General Electric, and Siemens. The conceptual design drew on research from Atomic Energy Research Establishment, coordination with Royal Society advisors, and technical exchange with competitors such as France's Commissariat à l'énergie atomique et aux énergies alternatives and Japan Atomic Energy Agency programs.
The reactor was a pool-type sodium-cooled fast reactor featuring a primary circuit, intermediate sodium loop, and steam generators supplied to a turbine set by manufacturers like Turbine Hall (Dounreay) contractors and engineering firms including English Electric and Metropolitan-Vickers. The vessel, fuel handling, and heat removal strategy were influenced by earlier experimental facilities at Dounreay Fast Reactor and concepts evaluated by Oak Ridge National Laboratory, Argonne National Laboratory, and CEA Marcoule. Design parameters such as thermal output, core geometry, and coolant velocity were benchmarked against reactors like Superphénix, EBR-II, and SNR-300. Project oversight involved regulators and advisory boards including the Nuclear Installations Inspectorate, the Health and Safety Executive, and parliamentary scrutiny from the House of Commons energy committees.
The core used mixed oxide fuel assemblies comprising plutonium and uranium enriched material fabricated with input from facilities connected to Sellafield, Springfields fuel manufacturing, and research at AERE Harwell. Fuel cycle strategies were informed by breeder reactor theory developed by scientists with affiliations to University of Cambridge, University of Oxford, and Imperial College London departments collaborating with industrial partners such as British Nuclear Fuels Limited. Neutron economy, breeding ratio targets, and fuel management techniques were compared with programs at BN-600, Fast Flux Test Facility, and JOYO. Refueling operations used hot cell technology and remote handling equipment analogous to systems at Sellafield Magnox Reprocessing Plant and Winfrith hot cell facilities, while radiological protection standards referenced guidance from Health Physics Society advisors and international norms from the International Commission on Radiological Protection.
Safety architecture incorporated multiple redundant decay heat removal paths, sodium leak detection systems, and inert gas blanketing practiced in designs from EBR-I through Superphénix. Containment and secondary systems drew from practices at Sizewell and Bradwell stations, and regulatory compliance interfaced with statutory frameworks influenced by the Nuclear Installations Act 1965 and regulatory precedent set in inquiries involving Windscale fire aftermath procedures. Incident response planning coordinated with regional emergency services including Highland Council resources and national contingency planning by the Civil Defence mechanisms and the Ministry of Health advisory structures.
Commissioned in 1974, the Prototype Fast Reactor operated during a period marked by energy crises, debates in the House of Commons over nuclear strategy, and shifts in policy under administrations led by figures such as Harold Wilson and Margaret Thatcher. The reactor experienced technical challenges familiar to peers like Monju and Phénix, prompting outages, inspections, and refurbishments managed by teams from UKAEA and contractors including British Nuclear Group. International observers from IAEA and delegations from France, Japan, United States, Germany, and the Soviet Union visited to study sodium technology, fuel breeding performance, and remote handling. Operational data contributed to scientific literature in journals associated with Institute of Physics, American Nuclear Society, and engineering societies including the Institution of Mechanical Engineers.
Following final shutdown in 1994, decommissioning proceeded under programs coordinated by successors to UKAEA, with involvement from Nirex planning groups, environmental regulators such as the Scottish Environment Protection Agency, and contractors skilled in nuclear decommissioning including Cammell Laird and international firms experienced at Sellafield. Lessons informed later projects like PRISM (reactor) proposals, academic research at University of Bristol and University of Manchester, and policy debates in the Department of Trade and Industry and Department of Energy and Climate Change. The site's legacy influenced safety standards, remote handling innovations, and waste management strategies incorporated into repositories discussed by the Committee on Radioactive Waste Management and planners studying options at Yucca Mountain and repository concepts in Finland and Sweden. The project remains cited in reviews of fast reactor viability by organizations such as the World Nuclear Association, OECD Nuclear Energy Agency, and the International Atomic Energy Agency.
Category:Nuclear reactors in the United Kingdom Category:Fast neutron reactors