A steam injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater. This provides SI with capability to use as a passive ECCS pump and also as a direct-contact feedwater heater that heats up feedwater by using extracted steam from the turbine. In order to develop a high reliability passive ECCS pump and a compact feedwater heater, it is necessary to quantify the characteristics between physical properties of the flow field. We carried out experiments to observe the internal behavior of the water jet as well as measure the velocity of steam jet using a laser Doppler velocimetry. Its performance depends on the phenomena of steam condensation onto the water jet surface and heat transfer in the water jet due to turbulence on to the phase-interface. The analysis was also conducted by using a CFD code with the separate two-phase flow models. With regard to the simplified feed-water system, size of four-stage SI system is almost the same as the model SI that had done the steam and water test that pressures were same as that of current ABWR. The authors also conducted the hot water supply system test in the snow for a district heating. With regard to the SI core cooling system, the performance tests results showed that the low-pressure SI core cooling system will decrease the PCT to almost the same as the saturation temperature of the steam pressure in a pressure vessel. As it is compact equipment, SI is expected to bring about great simplification and materials-saving effects, while its simple structure ensures high reliability of its operation, thereby greatly contributing to the simplification of the power plant for not only an ABWR power plant but also a small PWR/ BWR for district heating system.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4244-4
PROCEEDINGS PAPER
Development of Technologies on Innovative Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors: Part 10—Application to a Small District-Heating Reactor
Tadashi Narabayashi,
Tadashi Narabayashi
Hokkaido University, Sapporo, Japan
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Yoichiro Shimazu,
Yoichiro Shimazu
Hokkaido University, Sapporo, Japan
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Toshihiko Murase,
Toshihiko Murase
Hokkaido University, Sapporo, Japan
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Masatoshi Nagai,
Masatoshi Nagai
Hokkaido University, Sapporo, Japan
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Michitsugu Mori,
Michitsugu Mori
Tokyo Electric Power Company, Yokohama, Japan
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Shuichi Ohmori
Shuichi Ohmori
Tokyo Electric Power Company, Yokohama, Japan
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Tadashi Narabayashi
Hokkaido University, Sapporo, Japan
Yoichiro Shimazu
Hokkaido University, Sapporo, Japan
Toshihiko Murase
Hokkaido University, Sapporo, Japan
Masatoshi Nagai
Hokkaido University, Sapporo, Japan
Michitsugu Mori
Tokyo Electric Power Company, Yokohama, Japan
Shuichi Ohmori
Tokyo Electric Power Company, Yokohama, Japan
Paper No:
ICONE14-89753, pp. 923-931; 9 pages
Published Online:
September 17, 2008
Citation
Narabayashi, T, Shimazu, Y, Murase, T, Nagai, M, Mori, M, & Ohmori, S. "Development of Technologies on Innovative Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors: Part 10—Application to a Small District-Heating Reactor." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. Miami, Florida, USA. July 17–20, 2006. pp. 923-931. ASME. https://doi.org/10.1115/ICONE14-89753
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