scholarly journals FEASIBILITY STUDY OF A DUALPURPOSE NUCLEAR REACTOR POWER PLANT FOR THE FLORIDA KEYS

1964 ◽  
Author(s):  
Keyword(s):  
Power Plant ◽  
Feasibility Study ◽  
Nuclear Reactor ◽  
Florida Keys ◽  
Reactor Power ◽  
Reactor Power Plant

scholarly journals 600 MW FUSED SALT HOMOGENEOUS REACTOR POWER PLANT. Reactor Design and Feasibility Study

1956 ◽  
Author(s):  
R.W. Davies ◽  
D.H. Feener ◽  
W.A. Frederick ◽  
K.R. Goller ◽  
I. Granet ◽  
...  
Keyword(s):  
Power Plant ◽  
Feasibility Study ◽  
Reactor Design ◽  
Reactor Power ◽  
Plant Reactor ◽  
Homogeneous Reactor ◽  
Reactor Power Plant ◽  
Fused Salt

scholarly journals High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis

2016 ◽  
Vol 10 ◽  
pp. 00105 ◽  
Author(s):  
Michał Dudek ◽  
Marek Jaszczur ◽  
Katarzyna Skolik ◽  
Mateusz Malicki ◽  
Ludwik Pieńkowski
Keyword(s):  
High Temperature ◽  
Numerical Analysis ◽  
Power Plant ◽  
Nuclear Reactor ◽  
Reactor Power ◽  
Electricity Production ◽  
Reactor Power Plant

Temperature Transients in a Triple Heat Exchanger

1984 ◽  
Vol 198 (3) ◽  
pp. 145-154
Author(s):  
P C Chiu ◽  
E H K Fung
Keyword(s):  
Heat Exchanger ◽  
Nuclear Reactor ◽  
Reactor Power ◽  
Solar Heating ◽  
Inlet Temperature ◽  
Exchange Processes ◽  
Flow Experiments ◽  
Heating Plant ◽  
Reactor Power Plant ◽  
Secondary Fluid

A triple heat exchanger, so called because there are three heat exchange processes taking place in it, was built to simulate the system behaviour of a nuclear reactor power plant or a solar heating plant which is characterized by the two circulating loops of the fluid flow. Experiments were carried out to study the temperature transients under disturbances in secondary fluid inlet temperature and power output from immersion heaters. Numerical results were obtained from the weighted residual formulation of the proposed dynamic model and they were shown to be in general agreement with the two sets of experimental responses.

A High Effective Parallel Method for the Coupling Between Neutronics and Thermal-Hydraulic

2016 ◽  
Author(s):  
Xiaomeng Dong ◽  
Zhijian Zhang ◽  
Zhaofei Tian ◽  
Lei Li ◽  
Guangliang Chen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Decisive Role ◽  
Reactor Power ◽  
Coupling Method ◽  
Outlet Temperature

Multi-physics coupling analysis is one of the most important fields among the analysis of nuclear power plant. The basis of multi-physics coupling is the coupling between neutronics and thermal-hydraulic because it plays a decisive role in the computation of reactor power, outlet temperature of the reactor core and pressure of vessel, which determines the economy and security of the nuclear power plant. This paper develops a coupling method which uses OPENFOAM and the REMARK code. OPENFOAM is a 3-dimension CFD open-source code for thermal-hydraulic, and the REMARK code (produced by GSE Systems) is a real-time simulation multi-group core model for neutronics while it solves diffusion equations. Additionally, a coupled computation using these two codes is new and has not been done. The method is tested and verified using data of the QINSHAN Phase II typical nuclear reactor which will have 16 × 121 elements. The coupled code has been modified to adapt unlimited CPUs after parallelization. With the further development and additional testing, this coupling method has the potential to extend to a more large-scale and accurate computation.

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