Simulation of the Natural Convection Test of Phenix Reactor Using Modified ATHLET

2012 ◽  
Author(s):  
Chong Zhou ◽  
Klaus Huber ◽  
Xu Cheng
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Natural Convection ◽  
Fast Reactor ◽  
Atomic Energy Commission ◽  
Computer Code ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors ◽  
Alternative Energies

The sodium-cooled fast reactor (SFR) is gathering worldwide attention for its features of the fast-spectrum reactor and closed fuel recycle system. This paper presents the modification of the ATHLET code for application to SFRs. The thermal-hydraulic computer code ATHLET is developed by Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) in Germany for light water reactors analysis. In this paper, a sodium properties package is implemented in to the ATHLET code, and heat transfer correlations for sodium are also added for heat transfer prediction. To evaluate the capability of the modified code, the Phenix reactor, a SFR operated by French Alternative Energies and Atomic Energy Commission (CEA) from 1973 to 2009, is modeled. The scenario of transient from forced to natural convection is simulated and analyzed. The results are compared with the experimental data of the natural convection ultimate test of the Phenix facility. Results achieved so far indicate good applicability of the modified ATHLET code.

Performance of Containment Sprays for Light Water Reactors and Evaluation of the Heat Transfer

1981 ◽  
Vol 54 (1) ◽  
pp. 54-67 ◽  
Author(s):  
Mitsugu Tanaka ◽  
Hironori Watanabe ◽  
Kazuichiro Hashimoto ◽  
Yasuo Motoki ◽  
Mitsuo Naritomi ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors

Modeling of Spacer Influence on Post-Dryout Heat Transfer in Heated Channels

2006 ◽  
Author(s):  
Henryk Anglart
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Enhancement ◽  
Phenomenological Model ◽  
Nuclear Reactors ◽  
Light Water Reactors ◽  
Transfer Enhancement ◽  
Light Water ◽  
Operational Conditions ◽  
Transfer Processes ◽  
Water Reactors

Post-dryout heat transfer plays an important role in safe and economical operations of Light Water Reactors (LWR). This type of heat transfer is avoided under normal operational conditions of nuclear reactors; however, it may occur in transient or accidential situations. To estimate the risk of clad damages due to increase of temperature associated with the occurrence of post-dryout, it is necessary to properly model heat transfer processes under such conditions. The influence of various parameters on heat transfer downstream of spacer has been investigated. It is concluded that heat transfer enhancement due to spacers is largely under-predicted for flows with relatively low quality. For such flows the effect of droplets impinging heated walls is significant and must properly be taken into account. The phenomenological model presented in this paper shows a superior accuracy over correlations and presents a potential to capture the phenomenon of rewetting that occurs downstream of spacers.

EREC-STRESA: Web Database of Thermohydraulic Experiments on NPPs Safety

2008 ◽  
Author(s):  
Vladimir N. Blinkov ◽  
Mikhail V. Davydov
Keyword(s):  
Experimental Data ◽  
International Level ◽  
Light Water Reactors ◽  
Web Database ◽  
Web Based ◽  
Light Water ◽  
Large Scope ◽  
Water Reactors

There is a considerable amount of resources devoted to experimental databases in the field of NPPs safety at the international level. Most of them have no data concerning light water reactors of Russian type. EREC has gained a large scope of experimental data for such reactors. This paper presents the EREC-STRESA web-based database. It is the unique most complete database resulted from thermohydraulic experiments dedicated to analysis of Russian LWR NPPs safety.

Investigation of ATHLET System Code for Supercritical Water Applications

2014 ◽  
Author(s):  
J. Samuel ◽  
G. Lerchl ◽  
G. D. Harvel ◽  
I. Pioro
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Supercritical Water ◽  
Nuclear Reactor ◽  
High Pressures ◽  
Computer Code ◽  
Fluid Temperature ◽  
Bulk Fluid ◽  
Water Reactors ◽  
First Time

SuperCritical Water-cooled Reactors (SCWRs) are one of six Generation-IV nuclear-reactor concepts. They are expected to have high thermal efficiencies within the range of 45–50% owing to the reactor’s high pressures and outlet temperatures. Efforts have been made to study the supercritical phenomena both analytically and experimentally. However, codes that have been used to study the phenomena analytically have not been validated for supercritical water. The thermal-hydraulic computer code ATHLET (Analysis of THermal-hydraulics of LEaks and Transients) is used for analysis of anticipated and abnormal plant transients, including safety analysis of Light Water Reactors (LWRs) and Russian Graphite-Moderated High Power Channel-type Reactors (RBMKs). The range of applicability of ATHLET has been extended to supercritical water by updating the fluid- and transport-properties packages, thus enabling a transition from subcritical to supercritical fluid states. This extension needs to be validated using experimental data. In this work, the applicability of ATHLET code to predict supercritical-water behaviour in various heat-transfer conditions is assessed. Several well-known heat-transfer correlations for supercritical fluids are added to the code and applied for the first time in ATHLET simulations of experiments. A numerical model in ATHLET is created to represent an experimental test section and results for the heat transfer coefficient, bulk fluid temperature, and the tube inside-wall temperature are compared with the experimental data. The results from the ATHLET simulations are promising in the Normal and Enhanced Heat-Transfer Regimes. However, important phenomena such as Deteriorated Heat Transfer are currently not accurately predicted. While ATHLET can be used to develop preliminary design solutions for SCWRs, a significant effort in analysis of experimental work is required to make further advancements in the use of ATHLET for SCW applications.

S-Prism Reactor: The Fast Reactor for GNEP

2009 ◽  
Author(s):  
Charles Stratton
Keyword(s):  
Nuclear Waste ◽  
Fast Reactor ◽  
Nuclear Energy ◽  
Low Cost ◽  
Cost Effective ◽  
Nuclear Industry ◽  
Light Water Reactor ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors

GNEP (Global Nuclear Energy Partnership) has the objectives for a recycling program to reduce nuclear waste and reduce the risk of proliferation. These goals are important for the perception of the nuclear industry and for the industry to have a successful future. A fast reactor is much better suited for these goals than the existing Light Water Reactors or the development of an Advanced Light Water Reactor. The S-PRISM reactor is a fast reactor design by GE that is cost-effective and feasible for implementation, due to its low cost for design certification. The GNEP program has the ability to achieve its objectives for a recycling program by implementing the S-PRISM reactor.

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