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

Dynamic Simulation Research on Primary Coolant System of Sodium Cooled Fast Reactor

2012 ◽  
Author(s):  
Yang Yu ◽  
Yun Guo
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Safety Analysis ◽  
Operating Conditions ◽  
Cold Pool ◽  
Primary Coolant ◽  
Simulation Research ◽  
Flow And Heat Transfer ◽  
Comparison Of The Results ◽  
Pool Type

The Chinese Experimental Fast Reactor (CEFR) is a 65MWt/20MWe sodium cooled fast reactor. It is a pool-type reactor where the reactor and other internals such as pumps and intermediate heat exchangers (IHX) are immersed in a sodium pool. In this paper a one-dimensional dynamic code was developed to model the primary sodium circuit which included the reactor core, IHX, pumps, hot and cold pool etc. Moreover, the model of the property of sodium flow and heat transfer correlations was collected and compiled. This paper also discusses the mathematical models of various components of the primary sodium circuit, the numerical techniques to solve the models, the thermal-hydraulic studies of some design basis events such as the loss of primary pump or secondary pump accident etc, the comparison of the results of the code with that of the safety analysis report. Studies were conducted simulating both full and low power operating conditions. The dynamic code has been validated, and the results show that it has a benign response to some typical accidents. Finally, the model and code derived in this paper could be used in the safety analysis of pool-type sodium cooled fast reactor, and adopted in the development of CEFR simulation platform.

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 MELT-III: a neutronics, thermal-hydraulics computer program for fast reactor safety analysis. Volume II

1974 ◽  
Author(s):  
A.E. Waltar ◽  
W.L. Partain ◽  
D.C. Kolesar ◽  
L.D. O'Dell ◽  
A. Jr. Padilla ◽  
...  
Keyword(s):  
Computer Program ◽  
Fast Reactor ◽  
Safety Analysis ◽  
Thermal Hydraulics ◽  
Reactor Safety

Safety analysis of small long life CANDLE fast reactor

2008 ◽  
Vol 35 (5) ◽  
pp. 813-828 ◽  
Author(s):  
Mingyu Yan ◽  
Hiroshi Sekimoto
Keyword(s):  
Fast Reactor ◽  
Safety Analysis ◽  
Long Life

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
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