System Design and Analysis of a 900-MW(thermal) Lead-Cooled Fast Reactor

2010 ◽  
Vol 170 (1) ◽  
pp. 148-158
Author(s):  
Sang Ji Kim ◽  
Yonghee Kim ◽  
Sergi Hong ◽  
Chung Ho Cho ◽  
Jae-Hyuk Eoh ◽  
...  
Keyword(s):  
System Design ◽  
Fast Reactor

scholarly journals The Gas-Cooled Fast Reactor: Report on Safety System Design for Decay Heat Removal

2003 ◽  
Author(s):  
K. D. Weaver ◽  
T. Marshall ◽  
T. Y. C. Wei ◽  
E. E. Feldman ◽  
M. J. Driscoll ◽  
...  
Keyword(s):  
System Design ◽  
Fast Reactor ◽  
Heat Removal ◽  
Safety System ◽  
Decay Heat

Fast reactor decay heat removal: approach to the safety system design in Japan and Europe

1999 ◽  
Vol 193 (1-2) ◽  
pp. 45-54 ◽  
Author(s):  
B Farrar ◽  
J.C Lefèvre ◽  
S Kubo ◽  
C.H Mitchell ◽  
Y Yoshinari ◽  
...  
Keyword(s):  
System Design ◽  
Fast Reactor ◽  
Heat Removal ◽  
Safety System ◽  
Decay Heat

Development of Advanced Loop-Type Fast Reactor in Japan: Progress of Design Study Based on Preliminary Assessment Results

2010 ◽  
Author(s):  
Yoshihiko Sakamoto ◽  
Shoji Kotake ◽  
Kazumi Aoto ◽  
Mikio Toda
Keyword(s):  
System Design ◽  
Fast Reactor ◽  
Structural Integrity ◽  
Technology Development ◽  
Development Project ◽  
Reactor Vessel ◽  
Reactor System ◽  
Preliminary Assessment ◽  
Design Study ◽  
Seismic Force

The Japan sodium-cooled fast reactor (JSFR) is an advanced loop-type reactor concept which is investigated in the Fast Reactor Cycle Technology Development project in Japan. This paper describes some important progress on the JSFR design study and R&D discussed in a preliminary assessment for the first milestone of this project. As for the reactor system design, structural integrity against both thermal stress and seismic force was investigated. Then, the specification of the reactor vessel was established. Also, investigation of design options to extend a design margin against seismic force has been suggested. Regarding thermal hydraulics issues in the reactor vessel, design measures against cover gas entrainment and vortex cavitations have been introduced to the reactor system design based on R&D results. Further investigation is in progress for design optimization or improvement of preventive effect. The hot-leg piping design of primary cooling circuit was also established taking “Type-IV” damage into account.

System Design: What, Why, and How

1993 ◽  
Vol 38 (1) ◽  
pp. 101-102
Author(s):  
Charles G. Halcomb
Keyword(s):  
System Design
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