Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor

2021 ◽  
Author(s):  
Shibao Wang ◽  
Dalin Zhang ◽  
Yu Liang ◽  
Xinan Wang ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Fast Reactor ◽  
Reactor Core ◽  
Safety Analysis ◽  
Transfer Effect ◽  
System Safety

Safety Analysis of Fast Reactor Core with Uranium-Free Fuel for Actinide Transmutation

2003 ◽  
Vol 143 (3) ◽  
pp. 281-289 ◽  
Author(s):  
Igor Krivitski ◽  
Mikhail Vorotyntsev ◽  
Valentin Pyshin ◽  
Ludmila Korobeinikova
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Safety Analysis ◽  
Actinide Transmutation

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.

Research and development of a transient thermal–hydraulic code for system safety analysis of sodium cooled fast reactor

2021 ◽  
Vol 152 ◽  
pp. 107841
Author(s):  
Yang Yu ◽  
Dong Liu ◽  
Xiaoming Song ◽  
Zhongchun Li ◽  
Fengchen Guo ◽  
...  
Keyword(s):  
Research And Development ◽  
Fast Reactor ◽  
Safety Analysis ◽  
System Safety ◽  
Transient Thermal

Advanced Modeling of Multicomponent Vaporization/Condensation Phenomena for a Reactor Safety Analysis Code SIMMER-III

2002 ◽  
Author(s):  
Koji Morita ◽  
Tatsuya Matsumoto ◽  
Ryo Akasaka ◽  
Kenji Fukuda ◽  
Tohru Suzuki ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Phase Transition ◽  
Reactor Core ◽  
Safety Analysis ◽  
Mass Diffusion ◽  
Short Time Scale ◽  
Reactor Safety ◽  
Noncondensable Gases ◽  
Diffusion Limited ◽  
Multicomponent Flows

It is believed that the numerical simulation of thermal-hydraulic phenomena of multiphase, multicomponent flows in a reactor core is essential to investigate core disruptive accidents (CDAs) of liquid-metal fast reactors. A new multicomponent vaporization/condensation (V/C) model was developed to provide a generalized model for a fast reactor safety analysis code SIMMER-III, which analyzes relatively short-time-scale phenomena relevant to accident sequences of CDAs. The model characterizes the V/C process associated with phase transition through heat-transfer and mass-diffusion limited models to follow the time evolution of the rector core under CDA conditions. The heat-transfer limited model describes the nonequilibrium phase-transition processes occurring at interfaces, while the mass-diffusion limited model is employed to represent effects of noncondensable gases and multicomponent mixture on V/C processes. Verification of the model and method employed in the multicomponent V/C model of SIMMER-III was performed successfully by analyzing two series of condensation experiments.

scholarly journals Predicting unsteady heat transfer effect of vehicle thermal management system using steady velocity equivalent method

2021 ◽  
Vol 104 (2) ◽  
pp. 003685042110259
Author(s):  
Xiao Guoquan ◽  
Wang Huaming ◽  
Chen Lin ◽  
Hong Xiaobin
Keyword(s):  
Heat Transfer ◽  
Thermal Management ◽  
Management System ◽  
Exhaust System ◽  
Transfer Effect ◽  
Unsteady Heat Transfer ◽  
Thermal Management System ◽  
Comparison Results ◽  
Equivalent Method ◽  
Steady Velocity

In the process of vehicle development, the unsteady simulation of thermal management system is very important. A 3D-CFD calculation model of vehicle thermal management is established, and simulations were undertaken for uphill with full loads operations condition. The steady results show that the surface heat transfer coefficient increases to the quadratic parabolic relationship. The unsteady results show that the pulsating temperatures of exhaust and external airflow are higher than about 50°C and lower than 10°C, respectively, and the heat dissipating capacities are higher than about 11%. Accordingly, the conversion equivalent exhaust velocity increased by 1.67%, and the temperature distribution trend is basically the same as unsteady results. The comparison results show that the difference in the under-hood should be not noted, and that the predicted exhaust system surface temperatures using steady velocity equivalent method are low less 10°C than the unsteady results. These results show the steady velocity equivalent method can be used to predict the unsteady heat transfer effect of vehicle thermal management system, and the results obtained by this method are basically consistent with the unsteady results. It will greatly save computing resources and shorten the cycle in the early development of the vehicle thermal management system.

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