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Advanced gas-cooled reactor

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Advanced gas-cooled reactor
NameAdvanced gas-cooled reactor
GenerationGeneration II
Concept countryUnited Kingdom
DesignerUnited Kingdom Atomic Energy Authority
ManufacturerNational Nuclear Corporation
StatusOperational

Advanced gas-cooled reactor. An Advanced gas-cooled reactor is a type of nuclear reactor designed and primarily deployed in the United Kingdom. It represents the second generation of British gas-cooled reactors, developed as an improvement upon the earlier Magnox reactor design. These reactors use carbon dioxide as a coolant and graphite as a moderator, operating at higher temperatures and pressures to achieve greater thermal efficiency. The design was championed by the United Kingdom Atomic Energy Authority and led to the construction of 14 power stations, forming a significant part of the UK's electricity generation for decades.

Design and operation

The fundamental design utilizes carbon dioxide gas circulated under high pressure to remove heat from the nuclear core. This hot gas then passes through steam generators, producing steam to drive turbines connected to electrical generators. The reactor core is contained within a robust pre-stressed concrete pressure vessel, a key advancement over the steel vessels used in Magnox reactor stations. Operational control is maintained through the use of boron steel control rods inserted into the graphite moderator. The operating conditions, typically around 40 bar pressure and 640°C coolant outlet temperature, were a significant step forward from earlier designs, enabling improved thermodynamic efficiency. The primary circuit, including the gas circulators and heat exchangers, is entirely contained within the concrete pressure vessel, enhancing containment integrity.

Fuel and core

The core consists of thousands of graphite blocks that act as the neutron moderator, arranged to form channels for fuel assemblies and control rods. Fuel is in the form of cylindrical pellets of uranium dioxide enriched to around 2.5-3.5% uranium-235, a major departure from the metallic uranium fuel used in Magnox reactors. These pellets are stacked inside stainless steel fuel pins, which are then grouped into assemblies. The use of stainless steel cladding allows for the higher operating temperatures but has a greater neutron absorption penalty than Magnox alloy. The graphite moderator's integrity over the reactor's lifetime is critical, as it undergoes dimensional changes and stores Wigner energy due to neutron irradiation, requiring careful management and monitoring throughout the plant's operational life.

Safety features

Safety is underpinned by multiple redundant and diverse systems. The thick pre-stressed concrete pressure vessel provides a strong primary containment barrier. Independent shutdown systems include primary control rods and a secondary, diverse system often involving nitrogen injection into the coolant. The design incorporates extensive emergency core cooling systems to maintain carbon dioxide circulation and core heat removal under fault conditions. Operational safety cases rigorously analyze potential hazards such as carbon dioxide circuit depressurization, graphite moderator fires, and challenges to core cooling. The Office for Nuclear Regulation oversees the stringent regulatory framework ensuring these stations operate within strict safety limits, with lessons from incidents like the Windscale fire and Three Mile Island accident incorporated into safety practices.

Development and deployment

Development was initiated in the late 1950s by the United Kingdom Atomic Energy Authority following experience with the Calder Hall Magnox reactor. The prototype Windscale Advanced Gas-Cooled Reactor began operation in 1962. The commercial program was led by the Central Electricity Generating Board, with the first station, Hunterston B, opened in 1976. Subsequent stations, built in pairs, included Hinkley Point B, Hartlepool, Heysham, Dungeness B, and Torness. The construction was managed by consortia like the National Nuclear Corporation and involved major British engineering firms. While the program faced construction delays and cost overruns, it successfully provided a large portion of UK baseload electricity. All AGR stations are now undergoing defueling and decommissioning, managed by Magnox Ltd.

Comparison with other reactor types

Compared to its predecessor, the Magnox reactor, the AGR operates at higher temperature and pressure, uses enriched uranium dioxide fuel, and achieves a higher thermal efficiency, closer to 42%. Against the dominant global design, the pressurized water reactor, the AGR operates at higher temperatures but has a larger physical footprint and lower power density. Unlike light water reactors, it does not require a pressure vessel machined from forged steel, using concrete instead. The use of graphite as a moderator is shared with RBMK designs, though the coolant and safety philosophies differ vastly. While the AGR's carbon dioxide coolant is not as efficient a heat transfer medium as the water in a pressurized water reactor, it avoids phase change and associated challenges within the core. The design's complexity and unique British origin limited its export potential, contrasting with the widespread international adoption of designs from companies like Westinghouse Electric Company and Framatome.

Category:Nuclear reactor types Category:Nuclear power in the United Kingdom Category:Gas-cooled reactors