Sixth supplement to Publication 60231 (1967) General principles of nuclear reactor instrumentation Steam generating, direct cycle, heavy-water moderated reactors
|Publication Date:||1 January 1977|
|ICS Code (Reactor engineering):||27.120.10|
This supplement covers the general principles for instrumentation of steam generating, direct cycle, heavy-water moderated reactors having the following characteristics:
a) Slightly enriched fuel, metal-clad, contained within a pressure tube construction.
b) Cooled by forced circulation of light water, with boiling occurring within the pressure tube, and operating in a direct cycle mode.
c) Heavy-water moderator system which may have facilities for short-term control by variation of moderator level, and long-term control by variation of the concentration of a soluble neutron absorber.
The reactor core, the coolant circuits and the moderator circuit are usually located within an enclosed volume known as the containment. The purpose of the latter is to contain any activity which may result from a breach of the coolant or moderator circuits.