Page 65 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

40 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

GIF, 2014. Technology Roadmap Update for Generation IV Nuclear Energy Systems. OECD,
Paris, France.
Glasbrenner, H., Gr€ oschel, F., Grimmer, H., Patorski, J., Rohde, M., 2005. Expansion of solid-
ified lead bismuth eutectic. J. Nucl. Mater. 343, 341–348.
Gu enadou, D., Tkatshenko, I., Aubert, P., 2015. Plateau facility in support to ASTRID and the
SFR program: an overview of the first mock-up of the ASTRID upper plenum, MICAS.
In: NURETH16, Chicago, USA.
Guo, L., Morita, K., Tobita, Y., 2014. Numerical simulation of gas–solid fluidized beds by cou-
pling a fluid-dynamics model with the discrete element method. Ann. Nucl. Energy
72, 31–38.
Herranz, L., Lebel, L., Mascari, F., Spengler, C., 2018. Progress in modeling in-containment
source term with ASTEC-Na. Ann. Nucl. Energy 112, 84–93.
Hu, R., 2017. Development of a Reduced-Order Three-Dimensional Flow Model for Thermal
Mixing and Stratification Simulation During Reactor Transients. Argonne National Lab-
oratory (ANL), USA.
IAEA, 1995. Absorber materials, control rods and designs of shutdown systems for advanced
liquid metal fast reactors. IAEA Tecdoc 884, Vienna, Austria.
IAEA, 1999. Status of liquid metal cooled fast reactor technology. IAEA Tecdoc 1083, Vienna,
Austria.
IAEA, 2012. Status of fast reactor research and technology development. Technical Report 474,
ISBN 978–92–0-130610-4, Vienna, Austria.
IAEA, 2014. Summary report. In: Technical Meeting on Priorities in Modelling and Simulation
for Fast Neutron Systems. Vienna, Austria.
IEA/NEA, 2015. Technology Roadmap Nuclear Energy 2015, Paris, France.
IRSN, 2015. Review of Generation IV Nuclear Energy Systems. https://www.irsn.fr/EN/news
room/News/Pages/20150427_Generation-IV-nuclear-energy-systems-safety-potential-
overview.aspx.
Kamide, H., 2016. Progress of thermal hydraulic evaluation methods and experimental
studies on a sodium-cooled fast reactor and its safety in Japan. Nucl. Eng. Des.
312, 30–41.
Kamide, H., Hayashi, K., Isozaki, T., Nishimura, M., 2001. Investigation of core thermo-
hydraulics in fast reactors—interwrapper flow during natural circulation. Nucl. Technol.
133, 77–91.
Katsuyama, K., Nagamine, T., Matsumoto, S., Ito, M., 2003. Application of X-ray computer
tomography for observing the deflection and displacement of fuel pins in an assembly irra-
diated in FBR. J. Nucl. Sci. Technol. 40, 220–226.
Kayser, G., Charpenel, J., Jamond, C., Berthoud, G., Schleisiek, K., 1994. Main SCARABEE
lessons and most likely issue of the sub-assembly blockage accident. In: International Top-
ical Meeting, Obninsk, Russia.
Kennedy, G., Lamberts, D., Profir, M., Moreau, V., Van Tichelen, K., 2017. Experimental and
numerical study of the MYRRHA control rod system dynamics. In: ICAPP 2017, Fukui
and Kyoto, Japan.
Kimura, N., Miyakoshi, H., Kamide, H., 2010. Experimental study on thermal stratification
in a reactor vessel of innovative sodium-cooled fast reactor – mitigation approach of
temperature gradient across stratification Interface. J. Nucl. Sci. Technol. 47 (9),
829–838.
Longatte, E., Baj, F., Hoarau, Y., Braza, M., Ruiz, D., Canteneur, C., 2013. Advanced numerical
methods for uncertainty reduction when predicting heat exchanger dynamic stability
limits: review and perspectives. Nucl. Eng. Des. 258, 164–175.