Abstract
The Steam Generating Heavy Water Reactor system (SGHWR) was selected for development in the United Kingdom as an alternative to the Commercial Advanced Gas-Cooled Reactor (CAGR) in the late 1950’s. As an alternative, it was required to have diverse technical features such as coolant, moderator and pressure containment.
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Pickman, D.O., Gittus, J.H., Rose, K.M. (1979). Fuel for the SGHWR. In: Henley, E.J., Lewins, J., Becker, M. (eds) Advances in Nuclear Science and Technology. Springer, Boston, MA. https://doi.org/10.1007/978-1-4613-2862-9_4
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DOI: https://doi.org/10.1007/978-1-4613-2862-9_4
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