Published August 2018 | Version v1
Journal article

Investigation of the supersonic steam injector operation mode

  • 1. Laboratory of Nuclear System Safety Engineering, Division of Energy & Environmental Systems, Graduate School of Engineering, Hokkaido University, North 13 West 8, Kita-ku, Sapporo 060-8628 (Japan)
  • 2. Laboratory of Nuclear Power Infrastructure and Technologies, Division of Energy & Environmental Systems, Graduate School of Engineering, Hokkaido University, North 13 West 8, Kita-ku, Sapporo 060-8628 (Japan)

Description

Highlights: • Steam-water experiment was performed using central water-jet type steam injector (SI). • SI's pumping capability as a passive jet-pump was confirmed. • SI's operation mode was assessed using jet stability criteria. - Abstract: Steam injector (SI) operates as passive jet pump and heat exchanger, which is activated only by the high-pressure steam and water. SI possess simple geometry and does not require any external power supplies nor rotating machinery for the operation. It is capable of discharging subcooled water at higher pressure than the inlet, and operable as a passive jet pump. In addition, direct contact condensation heat transfer between steam and water-jet provides superior heat exchanging characteristics, more than 1,000 times that of shell and tube heat exchangers. Due to these advantageous features, SI has a great potential to be applied as a passive safety system of nuclear power plants including existing light water reactors and next generation reactors. In the present study, SI experiments targeting for the operating range and the pumping performance were carried out at 0.02–0.81 MPa inlet steam pressure and 0.21–0.80 kg/s inlet water flow rate. The SI body was manufactured by stainless steel equipped with overflow port. The water injection nozzle was designed with shaft-driving mechanism to adjust the axial location of the water jet and steam inlet area. During the experiment, SI's pump performance and operation mode were investigated by changing the inlet conditions. Maximum attainable discharge pressure and operation state of the SI were recorded at each inlet condition. In this study, liquid jet break-up length was considered to assess the SI's operation mode. Clear boundaries to explain the SI's operational range were obtained using the jet stability analysis. The research results presented here provides significant aspect to properly design operable SI as the passive safety system.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2018.05.002

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2018.05.002;
PII
S0029549318305168;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
334
Journal Page Range
p. 57-65
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.