scholarly journals NUMERICAL ANALYSIS OF THERMAL STRATIFICATION IN THE UPPER PLENUM OF THE MONJU FAST REACTOR

2013 ◽  
Vol 45 (2) ◽  
pp. 191-202 ◽  
Author(s):  
SEOK-KI CHOI ◽  
TAE-HO LEE ◽  
YEONG-IL KIM ◽  
DOHEE HAHN
Keyword(s):  
Numerical Analysis ◽  
Fast Reactor ◽  
Thermal Stratification

Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR)

2020 ◽  
Vol 138 ◽  
pp. 107222
Author(s):  
Mingjun Wang ◽  
Jing Chen ◽  
Dalin Zhang ◽  
Jing Zhang ◽  
Wenxi Tian ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Thermal Stratification ◽  
Numerical Study

F209 Fundamental Validation of Simulation Method for Thermal Stratification in Upper Plenum of Fast Reactor

2008 ◽  
Vol 2008.13 (0) ◽  
pp. 493-494
Author(s):  
Shuji OHNO ◽  
Hiroshi OHKI ◽  
Akihiro SUGAHARA ◽  
Hiroyuki OHSHIMA
Keyword(s):  
Fast Reactor ◽  
Thermal Stratification ◽  
Simulation Method

Numerical Analysis of Flow-Induced Vibration of Large Diameter Pipe With Short Elbow

2017 ◽  
Author(s):  
Shigeru Takaya ◽  
Tatsuya Fujisaki ◽  
Masaaki Tanaka
Keyword(s):  
Numerical Simulation ◽  
Numerical Analysis ◽  
Fast Reactor ◽  
Pressure Fluctuation ◽  
Cooling System ◽  
Large Diameter ◽  
Recirculation Region ◽  
Flow Induced Vibration ◽  
Scaled Model ◽  
Energy Agency

Japan Atomic Energy Agency is now conducting design study and R&D of an advanced loop-type sodium cooled fast reactor. The cooling system is planned to be simplified by employing a two-loop configuration and shortened piping with less elbows than a prototype fast reactor in Japan, Monju, in order to reduce construction costs and enhance economic performance. The design, however, increases flow velocity in the hot-leg piping and induces large flow turbulence around elbows. Therefore, flow-induced vibration (FIV) of a hot-leg piping is one of main concerns in the design. Numerical simulation is a useful method to deal with such a complex phenomenon. We have been developing numerical analysis models of the hot-leg piping using Unsteady Reynolds Averaged Navier-Stokes simulation with Reynolds stress model. In this study, numerical simulation of a 1/3 scaled-model of the hot-leg piping was conducted. The results such as velocity profiles and power spectral densities (PSD) of pressure fluctuations were compared with experiment ones. The simulated PSD of pressure fluctuation at the recirculation region agreed well with the experiment, but it was found some underestimation at other parts, especially in relatively high frequency range. Eigenvalue vibration analysis was also conducted using a finite element method. Then, stress induced by FIV was evaluated using pressure fluctuation data calculated by URANS simulation. The calculated stress generally agrees well the measurement values, which indicates the importance of precise evaluation of the PSD of pressure fluctuation at the recirculation region for evaluation of FIV of the hot-leg piping with a short elbow.

scholarly journals Numerical Analysis of JOYO MK-II Natural Circulation Test with Fast Reactor Plant Dynamics Code Super-COPD

2012 ◽  
Vol 78 (787) ◽  
pp. 468-470 ◽  
Author(s):  
Tomoyuki HIYAMA ◽  
Norihiro DODA ◽  
Hiroyuki OHSHIMA ◽  
Takashi IWASAKI
Keyword(s):  
Numerical Analysis ◽  
Fast Reactor ◽  
Natural Circulation ◽  
Reactor Plant ◽  
Plant Dynamics
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