Despite system thermal–hydraulic codes were extensively validated for transient simulations of LWR, several activities highlighted limited capabilities of these tools to model heat transfer within in-pool passive power removal system. Discrepancies with experimental results were related to the underestimate of pool boiling and film condensation heat transfer coefficients. Thus, the DIAEE of “Sapienza” University of Rome developed a modified version of RELAP5/Mod3.3, able to handle fundamental heat exchange phenomena involved in passive in-pool safety systems. A primary validation procedure has been performed for separated and integral effects. Dealing with nucleate boiling, the Root Mean Squared Relative Error (RMSRE) of wall superheat has ...
In nuclear safety operations, condensing heat transfer area is placed in a large pool of liquid to a...
The European Commission fourth framework programme project ‘Assessment of passive safety injection s...
The heat transfer model of the RELAP5/MOD3.1 (R5M3) code was extensively reviewed and assessed. The ...
This research investigates the capability of RELAP5-3D© to reproduce relevant thermal-hydraulic phen...
Passive systems are being implemented in several advanced reactors already constructed, under constr...
In recent years, a new class of reactor designs has been proposed that utilize passive safety system...
Within the field of research and development of innovative nuclear reactors, in particular Generatio...
Due to the character of the original source materials and the nature of batch digitization, quality ...
OSU MASLWR integral test facility, owned and operated at Oregon State University, represents a SMR c...
RELAP5/MOD3.1 was applied to the PO-IC-2 experiment performed in PIPER-ONE facility, which has been...
The first part of the thesis describes a method for using RELAP5 models to corroborate the scaling m...
RELAP5/MOD3.1 was applied to the PO-IC-2 experiment performed in PIPER-ONE facility, which has been ...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
In an attempt to understand the buildup of natural circulation in MTR pool type upward flow research...
One of the key areas in the design of advanced nuclear reactors is to develop a reliable Passive Con...
In nuclear safety operations, condensing heat transfer area is placed in a large pool of liquid to a...
The European Commission fourth framework programme project ‘Assessment of passive safety injection s...
The heat transfer model of the RELAP5/MOD3.1 (R5M3) code was extensively reviewed and assessed. The ...
This research investigates the capability of RELAP5-3D© to reproduce relevant thermal-hydraulic phen...
Passive systems are being implemented in several advanced reactors already constructed, under constr...
In recent years, a new class of reactor designs has been proposed that utilize passive safety system...
Within the field of research and development of innovative nuclear reactors, in particular Generatio...
Due to the character of the original source materials and the nature of batch digitization, quality ...
OSU MASLWR integral test facility, owned and operated at Oregon State University, represents a SMR c...
RELAP5/MOD3.1 was applied to the PO-IC-2 experiment performed in PIPER-ONE facility, which has been...
The first part of the thesis describes a method for using RELAP5 models to corroborate the scaling m...
RELAP5/MOD3.1 was applied to the PO-IC-2 experiment performed in PIPER-ONE facility, which has been ...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
In an attempt to understand the buildup of natural circulation in MTR pool type upward flow research...
One of the key areas in the design of advanced nuclear reactors is to develop a reliable Passive Con...
In nuclear safety operations, condensing heat transfer area is placed in a large pool of liquid to a...
The European Commission fourth framework programme project ‘Assessment of passive safety injection s...
The heat transfer model of the RELAP5/MOD3.1 (R5M3) code was extensively reviewed and assessed. The ...