ICONE23-1473 Improvement of transient analysis method of a sodium-cooled fast reactor with FAIDUS fuel sub-assemblies

2015 ◽  
Vol 2015.23 (0) ◽  
pp. _ICONE23-1-_ICONE23-1
Author(s):  
Kazuya Ohgama ◽  
Katsuyuki Kawashima ◽  
Shigeo Ohki
Keyword(s):  
Fast Reactor ◽  
Transient Analysis ◽  
Analysis Method

Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system

2018 ◽  
Vol 121 ◽  
pp. 324-334
Author(s):  
Xianan Du ◽  
Youqi Zheng ◽  
Liangzhi Cao ◽  
Hongchun Wu
Keyword(s):  
Fast Reactor ◽  
Transient Analysis ◽  
Code System

A Transient Analysis Method to Characterize the Trap Vertical Location in Nitride-Trapping Devices

2004 ◽  
Vol 25 (12) ◽  
pp. 816-818 ◽  
Author(s):  
H.-T. Lue ◽  
Y.-H. Shih ◽  
K.-Y. Hsieh ◽  
R. Liu ◽  
C.Y. Lu
Keyword(s):  
Transient Analysis ◽  
Analysis Method ◽  
Vertical Location ◽  
Trapping Devices

Safety Analysis of the Control Rod Drop Event Applying 3-D Neutronics/Thermal-Hydraulics Coupling Code SPARKLE

2009 ◽  
Author(s):  
Yuta Maruyama ◽  
Satoshi Imura ◽  
Junto Ogawa ◽  
Shuhei Miyake
Keyword(s):  
Power Distribution ◽  
Transient Analysis ◽  
Three Dimensional ◽  
Safety Margin ◽  
Safety Analysis ◽  
Thermal Hydraulics ◽  
Analysis Method ◽  
Dynamic Changes ◽  
Control Rod ◽  
Ejection Event

Mitsubishi Heavy Industries (MHI) has developed the SPARKLE code, which is a PWR plant system transient analysis code that includes a three-dimensional (3D) neutronics module coupled with a thermal-hydraulics module. MHI has performed a study of the applicability of the SPARKLE code to the events which are associated with dynamic changes in power distribution, such as the rod ejection event or the steam line break event. In this paper, MHI has applied the SPARKLE code to the control rod drop event (drop of multiple rods), which features such a power distribution change. In addition, the neutron flux detection is dependent on the location of the dropped rods in this event, which can be dynamically calculated in the SPARKLE code. By applying the SPARKLE code to the control rod drop event, it was confirmed that the safety margin for this event is sufficiently larger than the margin calculated using the current safety analysis method, even if the appropriate conservative assumptions are made.

Study on Seismic Analysis Method of Fast Reactor Plant with Seismic Isolation System

2020 ◽  
Vol 2020 (0) ◽  
pp. S10107
Author(s):  
Shigeki OKAMURA ◽  
Takahiro KINOSHITA ◽  
Hiroyuki NISHINO ◽  
Hidemasa YAMANO ◽  
Kenichi KURISAKA ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Seismic Isolation ◽  
Seismic Analysis ◽  
Analysis Method ◽  
Reactor Plant ◽  
Isolation System
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