Numerical analysis of liquid fall type gas entrainment in pool-type fast reactor

2021 ◽  
Vol 155 ◽  
pp. 108165
Author(s):  
Hao Yao ◽  
Yujian Huang ◽  
Yingwei Wu ◽  
Jing Zhang ◽  
Guanghui Su ◽  
...  
Keyword(s):  
Numerical Analysis ◽  
Fast Reactor ◽  
Gas Entrainment ◽  
Pool Type

Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor

Kerntechnik ◽  
2018 ◽  
Vol 83 (3) ◽  
pp. 232-236 ◽  
Author(s):  
D. L. Zhang ◽  
P. Song ◽  
S. Wang ◽  
X. Wang ◽  
J. Chen ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Cooling System ◽  
Pool Type ◽  
Code Development

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

A practical methodology devoted to pool‐type phenomena simulation in safety analysis for sodium‐cooled fast reactor

2020 ◽  
Author(s):  
Shibao Wang ◽  
Dalin Zhang ◽  
Suizheng Qiu ◽  
Guanghui Su ◽  
Wenxi Tian
Keyword(s):  
Fast Reactor ◽  
Safety Analysis ◽  
Pool Type

A CONCEPTUAL DESIGN STUDY OF POOL-TYPE SODIUM-COOLED FAST REACTOR WITH ENHANCED ANTI-SEISMIC CAPABILITY

2019 ◽  
Vol 2019.27 (0) ◽  
pp. 1651
Author(s):  
Shigenobu Kubo ◽  
Yoshitaka Chikazawa ◽  
Hiroyuki Ohshima ◽  
Masato Uchita ◽  
Takayuki Miyagawa ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Design Study ◽  
Pool Type

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.

Inertial impaction behavior of fuel particles under severe accident scenario in pool type sodium cooled fast reactor

2013 ◽  
Vol 256 ◽  
pp. 285-290 ◽  
Author(s):  
B. Thilak ◽  
P. Mangarjuna Rao ◽  
B.K. Nashine ◽  
P. Chellapandi
Keyword(s):  
Fast Reactor ◽  
Severe Accident ◽  
Inertial Impaction ◽  
Accident Scenario ◽  
Fuel Particles ◽  
Pool Type

scholarly journals Real-Scale Numerical Simulation of Gas Entrainment Phenomena in Fast Reactor

2011 ◽  
Vol 77 (776) ◽  
pp. 978-981
Author(s):  
Kei ITO ◽  
Tomoaki KUNUGI ◽  
Hiroyuki OHSHIMA ◽  
Takumi KAWAMURA
Keyword(s):  
Numerical Simulation ◽  
Fast Reactor ◽  
Gas Entrainment ◽  
Real Scale
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