TRACE V5 CODE APPLICATION DVI LINE BREAK LOCA USING ATLAS FACILITY
نویسندگان
چکیده
منابع مشابه
Integral Behavior of the Atlas Facility for a 3-inch Small Break Loss of Coolant Accident
Over the past 30 years, several large integral facilities have been utilized in order to understand transient behavior in nuclear power plants. The main objective of these integral facilities was to enhance our physical understanding of transient phenomena during LOCA or non-LOCA transients. An integral database was also used as a basis for the development and verification of thermal hydraulic ...
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Operators of nuclear power plants may not be equipped with sufficient information during a loss-of-coolant accident (LOCA), which can be fatal, or they may not have sufficient time to analyze the information they do have, even if this information is adequate. It is not easy to predict theprogressionof LOCAs innuclear power plants. Therefore, accurate informationon theLOCAbreakpositionandsize sh...
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Thermal hydraulic system codes are complex tools developed to estimate the transient behaviour of nuclear power plants (NPPs) during off-normal conditions. The evaluation of safety margins, the operator training, the optimization of the plant design and related emergency procedures are some of the major applications of these codes. Best estimate computer codes are used to calculate postulated a...
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The Ornstein-Zernike (OZ) equations [1] can be used to find probability distributions of atoms in fluid states where the primary unknowns are the radial pair correlation function and the direct correlation function. In order to specify conditions of the state, certain parameters such as density and temperature are chosen. While one can find a single solution to the OZ equations corresponding to...
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*Correspondence: Xiaojing Liu, School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan Road, Shanghai 200240, China e-mail: [email protected] During the loss of coolant accident (LOCA) of supercritical water-cooled reactor (SCWR), the pressure in the reactor system will undergo a rapid decrease from the supercritical pressure to the subcritical condition. T...
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ژورنال
عنوان ژورنال: Nuclear Engineering and Technology
سال: 2012
ISSN: 1738-5733
DOI: 10.5516/net.02.2012.713