Materials for the Very High Temperature Reactor (VHTR): A Versatile Nuclear Power Station for Combined Cycle Electricity and Heat Production

Authors

  • Wolfgang Hoffelner

DOI:

https://doi.org/10.2533/000942905777675435

Keywords:

Gas-cooled reactor, Generation iv, Helium gas-turbine, High-temperature materials, High-temperature reactor, Hydrogen

Abstract

The International Generation IV Initiative provides a research platform for the development of advanced nuclear plants which are able to produce electricity and heat in a combined cycle. Very high-temperature gas-cooled reactors are considered as near-term deployable plants meeting these requirements. They build on high-temperature gas-cooled reactors which are already in operation. The main parts of such an advanced plant are: reactor pressure vessel, core and close-to-core components, gas turbine, intermediate heat exchanger, and hydrogen production unit. The paper discusses the VHTR concept, materials, fuel and hydrogen production based on discussions on research and development projects addressed within the generation IV community. It is shown that material limitations might restrict the outlet temperature of near-term deployable VHTRs to about 950 °C. The impact of the high temperatures on fuel development is also discussed. Current status of combined cycle hydrogen production is elaborated on.

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Published

2005-12-12

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