In light water reactors, particularly the pressurized water reactor (PWR), the severity of a LOCA will limit how high the reactor power can operate. Although the best-estimate LOCA licensing methodology can provide the greatest margin on the PCT evaluation during LOCA, it generally takes more resources to develop. Instead, implementation of evaluation models required by the Appendix K of 10 CFR 50 upon an advanced thermal-hydraulic platform also can gain significant margin for the PCT calculation. The compliance of the current RELAP5-3D code with Appendix K of 10 CFR50 has been evaluated, and it was found that there are ten areas where code assessment and/or further modifications were required to satisfy the requirements set forth in the Ap...
The document deals with the description of results obtained by the Relap5 code in the planning of th...
The newly developed, advanced, light water reactor (LWR) simulation code, RELAP5, is used to analyze...
This thesis study presents the research work aimed to investigate the safety features of a next gene...
The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized...
The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized...
The assessment of the tools used for deterministic safety analysis and the compliance with the accep...
The application of RELAP5 at GRNSPG & NINE (Nuclear Research Group of San Piero a Grado–Nuclear and ...
One intension of the Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) program is...
The document deals with the description of results obtained by the Relap5 code in the post-test anal...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...
A thorough review was made of previous reports dealing with calculation of individual experiments to...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
The document deals with the description of results obtained by the Relap5 code in the planning of th...
The newly developed, advanced, light water reactor (LWR) simulation code, RELAP5, is used to analyze...
This thesis study presents the research work aimed to investigate the safety features of a next gene...
The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized...
The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized...
The assessment of the tools used for deterministic safety analysis and the compliance with the accep...
The application of RELAP5 at GRNSPG & NINE (Nuclear Research Group of San Piero a Grado–Nuclear and ...
One intension of the Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) program is...
The document deals with the description of results obtained by the Relap5 code in the post-test anal...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
ABSTRACT The PWR PACTEL test facility has recently been designed to support the safety studies of EP...
The licensing is a legal process to transfer the nuclear safety technology (developed and supported ...
A thorough review was made of previous reports dealing with calculation of individual experiments to...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
The document deals with the description of results obtained by the Relap5 code in the planning of th...
The newly developed, advanced, light water reactor (LWR) simulation code, RELAP5, is used to analyze...
This thesis study presents the research work aimed to investigate the safety features of a next gene...