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Coolant

Reactor coolant absorbs and removes heat from the reactor core. 

What is Coolant?

Stability and safety are crucial to the function of a nuclear reactor, coolant plays a pivotal role in this. As the reactions occur in the core of a nuclear plant, it produces heat. If this heat is not managed, the chain reactions would continue exponentially. The function of a coolant in a reactor is to prevent this, the coolant removes heat from the reactor core and transfers it to the secondary circuit for electricity generation.

There are multiple types of coolant, each with its own advantages and disadvantages and its selection is dependent on factors such as reactor design, safety considerations and intended reactor purpose.

Case Studies

Winfrith Nuclear Power Station

Following its opening in 1957, Winfrith became a centre for research and development. This included the main design which demonstrated a steam-generating heavy water reactor which provided power to the national grid and is currently undergoing decommissioning. This reactor was designed by the UKAEA, and looked to combine characteristics from both the CANDU reactor and PWR.

Oldbury Nuclear Power Station

Oldbury is a Magnox power station that is currently being decommissioned. During its life, Oldbury’s reactor was cooled by CO2 and produced enough electricity in a day to supply an area twice the size of Bristol. Oldbury was one of the last of the Magnox fleet to be built, beginning its service in 1967 and its production completing in 2012.

Sizewell B

Sizewell B is the UK’s only PWR, cooled by light water. Since its launch in 1995, it has generated 250 TWh of zero carbon electricity. Initially, the reactor was designed in the 1970’s, since then there have been modifications such as a passive Emergency Boratian System. Sizewell B has a target for a 20-year life extension beyond the current 2035 closure date.

An image of Sizewell A, a first generation Magnox reactor, in front of Sizewell B, a Pressurised Water Reactor. With a shingle beach in the foreground.

The Dragon

In the 1960s twelve countries banded together to create the first experimental high temperature gas-cooled reactor (HTGR) called The Dragon. This reactor utilised Helium as the reactor coolant and was operated successfully between 1966 and 1975. In principle, the project demonstrated better thermal efficiency, inherent safety, and lower power unit costs and some of the concepts used are being considered to be utilised by small modular reactors (SMRs).

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