SGHWR

Steam Generating Heavy Water Reactor (SGHWR) is a pressure tube type, heavy water moderated, light water cooled nuclear reactor. The steam generating heavy water reactor is in principle the same as a BWR but relies on a special heavy water material as the moderator whilst using conventional water as the primary coolant. They are similar in design to the CANDU, which uses pressure tubes and separates the coolant and moderator - the Gentilly-1 CANDU-BWR prototype was in fact a reactor of this type.

There is only a limited number of examples of this design the major one being at Winfrith in Dorset, UK, a 100 MW reactor which ceased operation on 1990 after 23 years of successful operation having reached the end of its design life. It was owned by United Kingdom Atomic Energy Authority.

References

[http://www.ukaea.org.uk/sites/winfrith_sghwr_reactor.shtml UKAEA SGHWR page]