Refine your search:     
Report No.
 - 
Search Results: Records 1-3 displayed on this page of 3
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Validation study of finite element thermal-hydraulics analysis code SPIRAL to a large-scale wire-wrapped fuel assembly at low flow rate condition

Yoshikawa, Ryuji; Imai, Yasutomo*; Kikuchi, Norihiro; Tanaka, Masaaki; Gerschenfeld, A.*

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.73 - 80, 2020/10

A finite element thermal-hydraulics simulation code SPIRAL has been developed in Japan Atomic Energy Agency (JAEA) to analyze the detailed thermal-hydraulics phenomena in a fuel assembly (FA) of Sodium-cooled Fast Reactors (SFRs). The numerical simulation of a large-scale sodium test for 91-pin bundle (GR91) at low flow rate condition was performed for the validation of SPIRAL with the hybrid k-e turbulence model to take into account the low Re number effect near the wall in the flow and temperature fields. Through the numerical simulation, specific velocity distribution affected by the buoyancy force was shown on the top of the heated region and the temperature distribution predicted by SPIRAL agreed with that measured in the experiment and the applicability of the SPIRAL to thermal-hydraulic evaluation of large-scale fuel assembly at low flow rate condition was indicated.

Journal Articles

IAEA NAPRO Coordinated Research Project; Physical properties of sodium

Passerini, S.*; Carardi, C.*; Grandy, C.*; Azpitarte, O. E.*; Chocron, M.*; Japas, M. L.*; Bubelis, E.*; Perez-Martin, S.*; Jayaraj, S.*; Roelofs, F.*; et al.

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.780 - 790, 2015/05

Oral presentation

Sodium experiments on coolability of decay heat removal system with dipped-type direct heat exchanger in PLANDTL2

Ezure, Toshiki; Onojima, Takamitsu; Tanaka, Masaaki; Gerschenfeld, A.*; Gorsse, Y.*; Li, S.*

no journal, , 

Japan Atomic Energy Agency has conducted a sodium experiment using the sodium facility (PLANDTL-2) within the framework of the ongoing research cooperation program with the French Alternative Energies and Atomic Energy Commission (CEA) to promote development of sodium cooled fast reactor. In this study, results on the decay heat removal experiments using dipped-direct heat exchanger (Dipped-DHX) will be presented to understand the effectiveness of the decay heat removal system.

3 (Records 1-3 displayed on this page)
  • 1