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Development of HTR Technology

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Modular High-temperature Gas-cooled Reactor Power Plant

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Abstract

The development of HTR is characterized by the use of coated particle fuel, graphite fuel elements and core structure and helium as coolant. For the fuel elements, different types have been developed: prismatic blocks in the USA, spherical fuel elements in Germany, modified prismatic blocks in Japan, and rod-type elements in Great Britain/OECD. These variants have advantages and disadvantages and some aspects are discussed in this chapter. The main goal in the beginning of the development was to show generally that the concepts with helium cooling are technically feasible and that high helium temperatures can be reached. High efficiency of energy conversion and a good neutron economy and the use of thorium were further points of interest in the first phase of the experimental reactors (UHTREX, AVR, Peach Bottom, DRAGON). In the second phase, the prototypes (THTR 300, Fort St. Vrain) have been built and the main requirement of these plants was to show that large reactor components can be constructed and that reactors with medium power can be operated. Furthermore, the planning and licensing work delivered the basis for further steps in the technology. Based on these experiences, large plants have been planned, which were estimated to be competitive to existing nuclear power plants (HTGR 1160 in USA, HTR 500 in Germany). Parallel to this concept using the steam cycle, the HHT power plant with the Brayton cycle was developed and planned in detail. After the accident in Three Miles Island (1979) and in Chernobyl (1986), the safety of the nuclear reactors became a dominating aspect and the modular HTR was developed with the goal to avoid core melting or overheating to unallowed high temperature and the release of large amounts of radioactive substances generally in case of severe accident. Different variants of this type were planned (as example HTR-Module (200 MWth), and HTR 100 in Germany, MHTR 350 in USA). These plants should be applied in several units on a site to realize large electrical power. Parallel to this, three own development process heat got rising importance. Planning work for the PR 500 and the PNP 500 and similar concepts in USA has been done and is available for future use of these promising technologies. China (HTR 10) and Japan (HTTR) introduced the HTR into their national programs and built their own experimental reactors. Today there is a phase of planning of commercial modular systems (China with the HTR-PM, France with the ANTARES, and other countries with interests in similar concepts). The VHTR was selected as a promising technology in the Generation IV development for future process heat utilization. In this chapter, the concepts mentioned before are explained and the main aspects are indicated. After the steps until now, which have shown that the HTR technology is technically feasible and can be licensed, now an optimization regarding safety, economy, and saving resources will be necessary. The tools and the knowledge to do this work are available. Some further testing of components and systems can help to accelerate the introduction of the technology to the market.

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  1. Institute for Reactor Safety and Reactor, RWTH Aachen University, Jülich, Germany

    Kurt Kugeler

  2. Institute of Nuclear and New Energy Tech, Tsinghua University, Beijing, China

    Zuoyi Zhang

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Kugeler, K., Zhang, Z. (2019). Development of HTR Technology. In: Modular High-temperature Gas-cooled Reactor Power Plant. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-57712-7_13

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