Abstract
The high-temperature engineering test reactor (HTTR) (Fig. 10.1) is the first high-temperature gas-cooled reactor in Japan. It first attained criticality in November 1998, and the reactor outlet temperature reached 850°C in December 2001, and 950°C in June 2004, both world firsts.
An erratum to this chapter can be found at http://dx.doi.org/10.1007/978-4-431-54195-0_12
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Bibliography
Yamashita K et al (2000) Critical test of the high-temperature engineering test reactor (HTTR). J Nucl Sci Technol 42(1):30–42
Fujikawa S et al (2002) Power up test of the high-temperature engineering test reactor (HTTR). J Nucl Sci Technol (Japanese Series) 1(4):361–372
Fujikawa S et al (2004) Achievement of reactor-outlet coolant temperature of 950 °C in HTTR. J Nucl Sci Technol 41(12):1245–1254
Tachibana Y et al (2003) Plan for first phase of safety demonstration tests of the High Temperature Engineering Test Reactor (HTTR). Nucl Eng Des 224(2):179–197
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Chapter 10 Exercises
Chapter 10 Exercises
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1.
During the steady operation of the HTTR, 13 pairs of the control rods use for reactor power under the condition of the control rod positions being flat (relative deviation = 20 mm). Explain the reason.
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2.
During the steady operation of the HTTR, the primary coolant pressure is controlled to be higher than the secondary coolant pressure. Explain the reason.
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Nakagawa, S. (2013). Actual Operation and Control of High-Temperature Engineering Test Reactor. In: Oka, Y., Suzuki, K. (eds) Nuclear Reactor Kinetics and Plant Control. An Advanced Course in Nuclear Engineering. Springer, Tokyo. https://doi.org/10.1007/978-4-431-54195-0_10
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DOI: https://doi.org/10.1007/978-4-431-54195-0_10
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