Nuclear Engineering and Technology

  • 제39권4호
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  • Pages.273-286
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  • 2007
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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RESEARCH ACTIVITIES ON A SUPERCRITICAL PRESSURE WATER REACTOR IN KOREA

  • 발행 : 2007.08.31
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초록

This paper presents the research activities performed to date for the development of a supercritical pressure water-cooled reactor (SCWR) in Korea. The research areas include a conceptual design of an SCWR with an internal flow recirculation, a reactor core conceptual design, a heat transfer test with supercritical $CO_2$, an adaptation of an existing safety analysis code to the supercritical pressure condition, and an evaluation of candidate materials through a corrosion study. Methods to reduce the cladding temperature are introduced from two different perspectives, namely, thermal-hydraulics and core neutronics. Briefly described are the results of an experiment on the heat transfer at a supercritical pressure, an experiment that is essential for the analysis of the subchannels of fuel assemblies and the analysis of a system safety. An existing system code has been adapted to SCWR conditions, and the process of a first-hand validation is presented. Finally, the corrosion test results of the candidate materials for an SCWR are introduced.

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참고문헌

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피인용 문헌

  1. The Turbulent Flows of Supercritical Fluids with Heat Transfer vol.45, pp.1, 2013, https://doi.org/10.1146/annurev-fluid-120710-101234
  2. PROPERTIES OF AQUEOUS SYSTEMS RELEVANT TO THE SCWR VIA MOLECULAR DYNAMICS SIMULATIONS vol.4, pp.1, 2015, https://doi.org/10.12943/ANR.2015.00041
  3. Rate of Hydrogen Combustion in Supercritical Water vol.121, pp.1, 2017, https://doi.org/10.1021/acs.jpcc.6b09615