References
- J. Yamashita, F. Kawamura, T. Mochida, Next-generation nuclear reactor systems for future energy, Hitachi Rev. 53 (3) (2004) 131-135.
- S. Uchikawa, T. Okubo, T. Kugo, H. Akie, R. Takeda, Y. Nakano, A. Ohunki, T. Iwamura, Conceptual design of innovativewater reactor for flexible fuel cycle (FLWR) and its recycle characteristics, J. Nucl. Sci. Technol. 44 (3) (2007) 277-284. https://doi.org/10.1080/18811248.2007.9711283
- Y. Fukaya, T. Okubo, S. Uchikawa, Investigation on spent fuel characteristics of reduced-moderation water reactor (RMWR), Nucl. Eng. Des 238 (2008) 1601-1611. https://doi.org/10.1016/j.nucengdes.2007.10.014
- W. Liu, A. Ohnuki, H. Yoshida, M. Kureta, K. Takase, H. Akimoto, Thermal feasibility analyses for the 1356MWe high conversion-type innovative water reactor for flexible fuel cycle, Heat Transfer Eng. 29 (8) (2008) 704-711. https://doi.org/10.1080/01457630801981614
- JAEA, Reduced-Moderation Water Reactor (RMWR), Status Report 80, release 04.04, JAEA., 2011. Available from: https://aris.iaea.org/sites/..%5CPDF%5CRMWR.pdf.
- R. Brogli, B. Kuczera, H. Moldaschl, W. Oldekop, Lessons learned from the PWHCR development, in: R. Chawla, R. Bohme, J. Dreier, R. Brogli, J. Axmann, H.D. Berger, C.H.M. Broeders, H. Hager, B. Kuczera, H. Moldaschl, W. Oldekop, S. Pelloni, N. Rouge, M. Schatz, R. Seiler, S. Yanar (Eds.), Contributions to Technical and Economic Aspects of High Converters, PSI-Bericht Nr. 71, Paul Scherrer Institut, June 1990, pp. 54-62.
- H. Tochihara, Y. Komano, M. Ishida, K. Narukawa, M. Umeno, Nuclear design for mixed moderator PWR, Prog. Nucl. Energ. 32 (314) (1998) 533-537. https://doi.org/10.1016/S0149-1970(97)00040-1
- D. Ito, M. Damsohn, H.-M. Prasser, M. Aritomi, Dynamic film thickness between bubbles and wall in a narrow channel, Exp. Fluids 51 (3) (2011) 821-833. Available from: http://link.springer.com/article/10.1007/s00348-011-1105-3.
- D. Ito, H.-M. Prasser, Measurement of two-phase flow structure in a narrow rectangular channel, in: G.U. Beltran, L.L. Castro Gomez (Eds.), Flow Measurement, InTech, 2012, pp. 73-94.
- M. Damsohn, H.-M. Prasser, High-speed liquid film sensor for two-phase flows with high spatial resolution based on electrical conductance, Flow Meas. Instrum. 20 (2009) 1-14. https://doi.org/10.1016/j.flowmeasinst.2008.06.006
- M. Damsohn, H.-M. Prasser, Experimental studies of the effect of functional spacers to annular flow in subchannels of a BWR fuel element, Nucl. Eng. Des. 240 (2010) 3126-3144. https://doi.org/10.1016/j.nucengdes.2010.05.032
- R. Zboray, J. Kickhofel, M. Damsohn, H.-M. Prasser, Coldneutron tomography of annular flow and functional spacer performance in a model of a boiling water reactor fuel rod bundle, Nucl. Eng. Des. 241 (2011) 3201-3215. https://doi.org/10.1016/j.nucengdes.2011.06.029
- D. Ito, H.-M. Prasser, Spatio-temporal measurement of liquid film thickness in tight-lattice double subchannels, The 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, NURETH-15, Pisa, Italy, May 12-17, 2013, Paper NURETH15-226. Available from: http://www.ans.org.
- P. Papadopoulos, Measurements in a Triangular Tight Lattice Channel with Mesh Sensors, Bachelor Thesis, ETH Zurich, Laboratory of Nuclear Energy Systems., 2011. Available from: hprasser@ethz.ch.
- R. Zboray, H.-M. Prasser, Neutron imaging of annular flows in a tight lattice fuel bundle model, Nucl. Eng. Des. 262 (2013) 589-599. https://doi.org/10.1016/j.nucengdes.2013.06.005
- M. Damsohn, Liquid films and droplet deposition in a BWR fuel element, PhD Thesis No. 19527, ETH Zurich., 2011. Available from: http://e-collection.library.ethz.ch/eserv/eth:2835/eth-2835-02.pdf.
- A. Saxena, H.-M. Prasser, Liquid Film Modeling in BWR Subchannel with Spacers, Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation (CFD4NRS-5), OECD/NEA & IAEA Workshop, Zurich, Switzerland, September 9-11, 2014, paper S02-4. Available from: https://www.oecd-nea.org/nsd/csni/cfd.
- K. Cramer, Investigation of the Influence of the Phase Transition on the Liquid Film Thickness in Vertical, Annular Two-phase Flow, Master thesis, ETH Zurich., April 2014. Available from: hprasser@ethz.ch.
- A. Saxena, R. Zboray, H.-M. Prasser, Simulations and Measurements of Adiabatic Annular Flows in a Triangular, Tight Lattice Nuclear Fuel Bundle Model, Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation (CFD4NRS-5), OECD/NEA & IAEA Workshop, Zurich, Switzerland, September 9-11, 2014, paper S02-1. Available from: https://www.oecd-nea.org/nsd/csni/cfd.
- R. Zboray, Ch. Bolesch, H.-M. Prasser, Neutron and X-ray imaging techniques for nuclear fuel rod bundle optimization and development, SWINTH-2016, Livorno, June 15-17, 2016, paper 17. Available from: hprasser@ethz.ch.
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