This paper presents assessment of the capacity of W7-X venting system in response to in-vessel LOCA, rupture of 40 mm diameter pipe during operation mode “baking.” The integral analysis of the coolant release from the cooling system, pressurisation of PV, and response of the venting system is performed using RELAP5 code. The same coolant release rate was introduced to the COCOSYS code, which is a lumped-parameter code developed for analysis of processes in containment of the light water reactors and the detailed analysis of the plasma vessel and the venting system is performed. Different options of coolant release modeling available in COCOSYS are compared to define the base case model, which is further used for assessment of the other para...
Whereas earlier analyses of the integrity of the reactor pressure vessel of NPP Stade (KKS) under em...
The RELAP5 code has been developed for best estimate transient simulation of light water reactor coo...
This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the ...
Computer modeling codes represent a crucial tool to support the design of future fusion plants. Sinc...
The principal objectives of this thesis are to assess the operability of the VVPSS small loca tank(S...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
Chilled Water System (CHWS-1) is an ITER safety cooling system comprised of two independent and segr...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
Being the Vacuum Vessel Pressure Suppression System (VVPSS) one of the most important passive safety...
The newly developed, advanced, light water reactor (LWR) simulation code, RELAP5, is used to analyze...
The Westinghouse Nuclear Safety Advisory Letter NSAL-09-8 investigated the possibility of presence o...
The document (in Italian) deals with the analysis by computer code RELAP4 of experimental data measu...
This study investigated the thermal hydraulic issues in the Containment Filtered Venting System (CFV...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
Whereas earlier analyses of the integrity of the reactor pressure vessel of NPP Stade (KKS) under em...
The RELAP5 code has been developed for best estimate transient simulation of light water reactor coo...
This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the ...
Computer modeling codes represent a crucial tool to support the design of future fusion plants. Sinc...
The principal objectives of this thesis are to assess the operability of the VVPSS small loca tank(S...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
Chilled Water System (CHWS-1) is an ITER safety cooling system comprised of two independent and segr...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
Being the Vacuum Vessel Pressure Suppression System (VVPSS) one of the most important passive safety...
The newly developed, advanced, light water reactor (LWR) simulation code, RELAP5, is used to analyze...
The Westinghouse Nuclear Safety Advisory Letter NSAL-09-8 investigated the possibility of presence o...
The document (in Italian) deals with the analysis by computer code RELAP4 of experimental data measu...
This study investigated the thermal hydraulic issues in the Containment Filtered Venting System (CFV...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
Whereas earlier analyses of the integrity of the reactor pressure vessel of NPP Stade (KKS) under em...
The RELAP5 code has been developed for best estimate transient simulation of light water reactor coo...
This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the ...