Development of a sub-channel thermal hydraulic analysis code and its application to lead cooled fast reactor

2017 ◽  
Vol 117 ◽  
pp. 443-451 ◽  
Author(s):  
Shuzhou Li ◽  
Liankai Cao ◽  
Muhammad Shehzad Khan ◽  
Hongli Chen
Keyword(s):  
Fast Reactor ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis

Multi channel thermal hydraulic analysis of gas cooled fast reactor using genetic algorithm

2012 ◽  
Author(s):  
R. Z. Drajat ◽  
Z. Su'ud ◽  
E. Soewono ◽  
A. Y. Gunawan
Keyword(s):  
Genetic Algorithm ◽  
Fast Reactor ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis

Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer

2018 ◽  
Vol 114 ◽  
pp. 198-205
Author(s):  
Seong Dae Park ◽  
Han Seo ◽  
Yeong Shin Jeong ◽  
Dong Wook Jerng ◽  
In Cheol Bang
Keyword(s):  
Fast Reactor ◽  
Reactor Fuel ◽  
Hydraulic Analysis ◽  
Sodium Fast Reactor ◽  
Fuel Bundle ◽  
Fast Reactor Fuel ◽  
Thermal Hydraulic Analysis

Modeling of Thermal Hydraulic Characteristics for a LBE-Cooled Fast Reactor Helical Coiled Type Steam Generator

2020 ◽  
Author(s):  
Xueyou Ding ◽  
Qinglong Wen ◽  
Zhiqiang Chen ◽  
Shenhui Ruan ◽  
Cheng Cheng
Keyword(s):  
Steam Generator ◽  
Fast Reactor ◽  
Fluid Model ◽  
Load Condition ◽  
Transfer Model ◽  
Hydraulic Parameters ◽  
Mechanism Analysis ◽  
Hydraulic Analysis ◽  
Analysis Model ◽  
Thermal Hydraulic Analysis

Abstract Lead and Bismuth Eutectic (LBE) cooled fast reactor is attracting attention due to its advantages in safety. A thermal hydraulic analysis model is developed for an LBE cooled fast reactor helical coiled type steam generator, which could be used for predicting thermal hydraulic parameters distribution along the length of the tube. Based on two fluid model, the mathematical heat transfer model includes six regions: single water and vapor, subcooled boiling, saturated boiling, transition boiling and film boiling. In order to describe the heat and mass transfer between phases, the interphase model is presented. The steam generator is simplified with single tube concept and all the flow variables are evaluated at each point of the grid in which the domain is discretized. Full load condition and a postulated scenario, such a flow rate step changed in secondary side, is calculated in this study. The results showed that the changing process of the thermal hydraulic parameters of helically coiled steam generator conforms to the qualitative mechanism analysis results of thermal hydraulic analysis.

Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements

2019 ◽  
Vol 5 (3) ◽  
Author(s):  
Guido Mazzini ◽  
Miloš Kynčl ◽  
Marek Ruščák ◽  
Miroslav Hrehor ◽  
Alis Musa ◽  
...  
Keyword(s):  
Experimental Data ◽  
High Temperature ◽  
Fast Reactor ◽  
Research Center ◽  
Experimental Measurements ◽  
Water Coolant ◽  
Hydraulic Analysis ◽  
Collaborative Project ◽  
Systems Simulation ◽  
Thermal Hydraulic Analysis

This paper focuses on the TRACE code assessment for helium-cooled systems thermal-hydraulic analysis. In the frame of the GoFastR (gas cooled fast reactor) European Collaborative Project, ENEA has offered some selected experimental data for the organization of a benchmark exercise aimed at the validation of the system and CFD codes for the gas reactor transient analyses. One of the Research Center Řež teams participated in it with a CFD code application. Now, the experimental data are used in order to assess the TRACE code for the ongoing high-temperature helium loop (HTHL-2) licensing process. The results of the TRACE calculations agreed very well with the experimental measurements (often within the experimental uncertainties) data provided by the He-FUS3 facility, indicating that the code, despite developed for water coolant applications, if an appropriately tuned input is adopted, it can also be suitable for reasonably accurate gas technology thermo-hydraulic simulations.

Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor

2013 ◽  
Vol 68 ◽  
pp. 65-78 ◽  
Author(s):  
Y.W. Wu ◽  
Xin Li ◽  
Xiaolei Yu ◽  
S.Z. Qiu ◽  
G.H. Su ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Fast Reactor ◽  
Liquid Sodium ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis
Sign in / Sign up

Export Citation Format

Share Document