Development and application of 3D pool-type sodium cooled fast reactor system analysis program

2021 ◽  
pp. 104027
Author(s):  
Peng Du ◽  
Qingwen Xiong ◽  
Jianqiang Shan ◽  
Jian Deng ◽  
Wei Chen ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Reactor System ◽  
Analysis Program ◽  
Pool Type

Basic verification of THACS for sodium-cooled fast reactor system analysis

2015 ◽  
Vol 76 ◽  
pp. 1-11 ◽  
Author(s):  
Zaiyong Ma ◽  
Nina Yue ◽  
Meiyin Zheng ◽  
Benxue Hu ◽  
Guanghui Su ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Reactor System

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 Development of System Analysis Program of Liquid Rocket Engine I

2013 ◽  
Vol 17 (4) ◽  
pp. 56-62
Author(s):  
Sang-Bok Lee ◽  
Min Son ◽  
Jongcheol Seo ◽  
Taekyu Lim ◽  
Tae-Seong Roh ◽  
...  
Keyword(s):  
System Analysis ◽  
Rocket Engine ◽  
Liquid Rocket Engine ◽  
Analysis Program ◽  
Liquid Rocket

scholarly journals Development of Advanced Radiation Resistant ODS Steel for Fast Reactor System Applications

2015 ◽  
Vol 03 (03) ◽  
pp. 125-128 ◽  
Author(s):  
Tae Kyu Kim ◽  
Sanghoon Noh ◽  
Suk Hoon Kang ◽  
Hyun Ju Jin ◽  
Ga Eon Kim
Keyword(s):  
Fast Reactor ◽  
Reactor System ◽  
Ods Steel ◽  
Radiation Resistant

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

Performance of Sodium Natural Circulation Loop for Passvie Decay Heat Removal

2008 ◽  
Author(s):  
Hae-Yong Jeong ◽  
Kwi-Seok Ha ◽  
Won-Pyo Chang ◽  
Yong-Bum Lee ◽  
Dohee Hahn ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Natural Circulation ◽  
Heat Removal ◽  
Circulation Loop ◽  
Ambient Atmosphere ◽  
Steady State Condition ◽  
Decay Heat ◽  
Natural Circulation Loop ◽  
Test Loop

The Korea Atomic Energy Research Institute (KAERI) is developing a Generation IV sodium-cooled fast reactor design equipped with a passive decay heat removal circuit (PDRC), which is a unique safety system in the design. The performance of the PDRC system is quite important for the safety in a simple system transient and also in an accident condition. In those situations, the heat generated in the core is transported to the ambient atmosphere by natural circulation of the PDRC loop. It is essential to investigate the performance of its heat removal capability through experiments for various operational conditions. Before the main experiments, KAERI is performing numerical studies for an evaluation of the performance of the PDRC system. First, the formation of a stable natural circulation is numerically simulated in a sodium test loop. Further, the performance of its heat removal at a steady state condition and at a transient condition is evaluated with the real design configuration in the KALIMER-600. The MARS-LMR code, which is developed for the system analysis of a liquid metal-cooled fast reactor, is applied to the analysis. In the present study, it is validated that the performance of natural circulation loop is enough to achieve the required passive heat removal for the PDRC. The most optimized modeling methodology is also searched for using various modeling approaches.

System reliability: An example of nuclear reactor system analysis

1984 ◽  
Vol 7 (2) ◽  
pp. 89-121 ◽  
Author(s):  
R. Coudray ◽  
J.M. Mattei
Keyword(s):  
System Reliability ◽  
System Analysis ◽  
Nuclear Reactor ◽  
Reactor System
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