Advanced gas-cooled reactor

From Free net encyclopedia

Image:AGR reactor schematic.png An Advanced Gas Cooled Reactor (AGR) is a type of nuclear reactor. These are the second generation of British gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. The fuel is uranium oxide pellets, enriched to 2.5-3.5%, in stainless steel tubes. The carbon dioxide circulates through the core, reaching 640°C and then passes through boiler (steam generator) assemblies outside the core but still within the steel lined, reinforced concrete pressure vessel. Control rods penetrate the moderator and a secondary shutdown system involves injecting nitrogen into the coolant or releasing boron ball shutdown devices.

AGR power stations are configured with two reactors, each reactor with a power output of between 555 MWe and 625 MWe. [1]

The design of the AGR was such that the final steam conditions at the boiler stop valve were identical to that of conventional power stations. Thus the same design of turbo-generator plant could be used. In order to obtain high temperatures, yet ensure useful graphite core life (graphite oxidises readily in CO₂ at high temperature) re-entrant flow is utilised, ensuring that the graphite core temperatures do not vary too much from those seen in a Magnox station.

The AGR has a good thermal efficiency (electricity generated/heat generated ratio) of about 41%, which is better than modern pressurized water reactors which have a typical thermal efficiency of 34%<ref name=shultis_and_faw>{{cite book

| last = Shultis
| first = J. Kenneth
| coauthors = Richard E. Faw
| year = 2002
| title = Fundamentals of Nuclear Science and Engineering
| publisher = Marcel Dekker
| id = ISBN 0-8247-0834-2

}}</ref>. This is largely due to the higher coolant outlet temperature of about 640°C practical with gas cooling, compared to about 325°C for PWRs. However the reactor core has to be larger for the same power output, and the fuel burnup ratio at discharge is lower so the fuel is used less efficiently, countering the thermal efficiency advantage [2].

The AGR was developed from the Magnox reactor, also graphite moderated and CO₂ cooled, a number of which are still operating in UK. The Magnox used natural uranium fuel in metal form and magnesium based cladding.

The original design concept of the AGR was to use a beryllium based cladding. When this proved unsuitable, the enrichment level of the fuel was raised to allow for the higher neutron capture losses of stainless steel cladding. This significantly increased the cost of the power produced by an AGR.

Like the Magnox, CANDU and RBMK reactors, and in contrast to the light water reactors, AGRs are designed to be refuelled without being shut down first, though a number of nuclear safety issues were identified in relation to this and so all AGRs either refuel at part load or when shut down.

The prototype AGR at the Sellafield (Windscale) site is in the process of being decommissioned. This project is also a study of what is required to decommission a nuclear reactor safely.

Currently there are seven nuclear generating stations each with two operating AGRs in the United Kingdom. They are all owned and operated by British Energy. These are located at Dungeness B, Hartlepool, Heysham 1, Heysham 2, Hinkley Point B, Hunterston B and Torness.

[edit]