Emergency containment
Introduction
Containment building, in its most common use, is a structure made of concrete, steel or a combination of both, built to enclose a nuclear reactor inside. It is designed so that, in case of emergency, it contains a release of radioactive gases even if these reach pressures in the range of 60 to 200 psi (4 to 13.6 atmospheres). Containment is the last barrier to a radioactive release, the first barrier being the ceramic itself of which the fuel is made, the second the metal sheaths that cover this fuel and the third the reactor vessel and the cooling system.
Design
The containment building is usually a watertight steel structure that encloses the reactor and is isolated from the outside atmosphere. Steel can be used alone or together with concrete armor. In the United States, the design and thickness of concrete containment and shielding is governed by federal regulations (10 CFR 50.55a).[1].
During normal operation, containment is sealed and access is through hatches similar to those used on ships. Air temperature and core radiation limit the time people can remain inside containment when the plant is operating at full power. Containment is designed to completely isolate and contain a core meltdown, putting it in a worst-case scenario called a design basis accident. Although there are redundant systems that prevent a possible merger, it is assumed in principle that this could happen, conditioning the characteristics of the containment. For its design, a break in the pipes of the reactor vessel is considered, which would cause a loss of coolant accident (LOCA) where the water inside the reactor vessel would escape into the containment and evaporate. The increase in pressure that this accident would cause inside the containment would trigger the containment sprinklers to condense that steam and thus reduce the pressure inside it. A rapid shutdown of the reactor (SCRAM) would begin very shortly after the breakage. Safety systems would close non-essential lines within the sealed containment by closing isolation valves. Emergency core cooling systems would quickly activate to cool the fuel and prevent melting. The exact sequence of these events depends on the reactor design. For an advanced boiling water reactor (ABWR) see pages 15A-37 and -38 of this document, for a CANDU see slides 21, 23 and 25 of this presentation.
In the United States and in US-designed reactors such as Spain or Mexico, containment buildings are subject to periodic (CILRTs), both to identify a possible leak in an accident or to locate and fix leak paths. .