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Engineering demonstration reactors: A stepping stone on the path to deployment of advanced nuclear energy in the United States

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  • Brown, Nicholas R.

Abstract

Nuclear energy is an important ultra-low carbon electricity source. Engineering demonstration reactors, such as Shippingport for Pressurized Water Reactor technology, have been used to advance nuclear reactor technology to deployment. It may be necessary to develop similar engineering demonstration reactors for other reactor concepts that have not yet been built. This paper reviews the historical role of engineering demonstration reactors and highlights the potential for future engineering demonstrations of Fluoride Salt-Cooled High Temperature Reactors (FHRs) and Molten Chloride Fast Reactors (MCFRs). Future engineering demonstration reactors could significantly accelerate deployment of larger-scale FHRs and MCFRs by the advanced nuclear industry via cost and risk reduction. Experience in the United States shows that sustained investment in a public-private partnership, such as the current Advanced Reactor Demonstration Program, is essential for deployment of advanced reactor technologies that have never been built before. The National Reactor Innovation Center at Idaho National Laboratory and Clinch River Site near Oak Ridge National Laboratory are examples of ideal locations for these demonstrations.

Suggested Citation

  • Brown, Nicholas R., 2022. "Engineering demonstration reactors: A stepping stone on the path to deployment of advanced nuclear energy in the United States," Energy, Elsevier, vol. 238(PA).
    • Handle: RePEc:eee:energy:v:238:y:2022:i:pa:s0360544221019988
    DOI: 10.1016/j.energy.2021.121750
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    References listed on IDEAS

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    1. Frederik Reitsma & Peter Woods & Martin Fairclough & Yongjin Kim & Harikrishnan Tulsidas & Luis Lopez & Yanhua Zheng & Ahmed Hussein & Gerd Brinkmann & Nils Haneklaus & Anand Rao Kacham & Tumuluri Sre, 2018. "On the Sustainability and Progress of Energy Neutral Mineral Processing," Sustainability, MDPI, vol. 10(1), pages 1-18, January.
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    Cited by:

    1. Hui, Jiuwu, 2024. "Coordinated discrete-time super-twisting sliding mode controller coupled with time-delay estimator for PWR-based nuclear steam supply system," Energy, Elsevier, vol. 301(C).
    2. Haneklaus, Nils & Qvist, Staffan & Gładysz, Paweł & Bartela, Łukasz, 2023. "Why coal-fired power plants should get nuclear-ready," Energy, Elsevier, vol. 280(C).
    3. Song, Houde & Liu, Xiaojing & Song, Meiqi, 2023. "Comparative study of data-driven and model-driven approaches in prediction of nuclear power plants operating parameters," Applied Energy, Elsevier, vol. 341(C).

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