Publication Laka-library:
Britain's SGHWR (Heavy water)
| Author | UKAEA |
| Date | April 1975 |
| Classification | 2.05.9.90/04 (UNITED KINGDOM - OTHER FACILITIES) |
| Front | 
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From the publication:
The SGHWR System The Steam Generating Heavy Water Reactor is a direct cycle, pressure tube reactor, using light water as the coolant and heavy water as the principal moderator. The reactor core consists of banks of pressure tubes which are made of zirconium alloy and are located within, but separated from, the tubes of a tank (the calandria) which contains the heavy water moderator at low pressure. About 30% of the moderation in the reactor takes place in the light water coolant thereby reducing appreciably the heavy water inventory. Furthermore, since the heavy water temperature does not exceed 80°C and the pressures in the moderator circuit are low, leakage losses of the expensive heavy water can be maintained at a very low level. The fuel is slightly enriched (approx. 2 %) uranium dioxide pellets clad in zirconium alloy and arranged in 36-rod clusters. Fuel clusters are positioned within the vertical pressure tubes and the fission heat generated causes partial boiling of the upward flowing coolant. The steam produced is separated from the water, in steam drums, and passes directly to the turbine. The water passes to the lower part of the drum and mixes with the condensate returning from the turbine condenser through the feed train and the full flow polishing plant, before recirculation to the core. The calandria is surrounded by water-filled neutron shield tanks so that coolant circuit components other than the pressure tubes are protected from significant neutron radiation.
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