This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the breeder primary cooling loop inside a heat exchanger (once through steam generator). After the detection of the loss of pressure inside the primary loop, a plasma shutdown is actuated with a consequent plasma disruption, isolation of the secondary loop, and shutoff of the pumps in the primary; no other safety counteractions are postulated. The objective of the work is to analyze the pressurization of the primary and secondary sides to show that the accidental overpressure in the two sides of the steam generators is safely accommodated. Furthermore, the effect of the plasma disruption on the FW, in terms of temperatures, should be analyzed. La...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant (N...
After emergency shutdown of high-temperature-gas-cooled reactor, the residual heat of the reactor co...
This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the ...
A total loss of all heat sinks is considered a severe accident with a low probability of occurrence....
A total loss of all heat sinks is considered a severe accident with a low probability of occurrence....
In this paper some contributions are provided to the development of a European Lead-cooled System, k...
Chilled Water System (CHWS-1) is an ITER safety cooling system comprised of two independent and segr...
The steam generator in a pressurized water reactor power plant acts as a fission product barrier bet...
A number of Nuclear Power Plants (NPPs) with Pressurized Water Reactors (PWR) in the world have repl...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
The thesis deals with the development and set-up of a specific MELCOR 1.8.6 Fusion Version nodalizat...
The Steam Generator Tube Rupture (SGTR) postulated event constitutes one of the most hazardous safet...
The tube rupture accident is one among the most risk-dominant events at the nuclear power plants. Se...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant ar...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant (N...
After emergency shutdown of high-temperature-gas-cooled reactor, the residual heat of the reactor co...
This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the ...
A total loss of all heat sinks is considered a severe accident with a low probability of occurrence....
A total loss of all heat sinks is considered a severe accident with a low probability of occurrence....
In this paper some contributions are provided to the development of a European Lead-cooled System, k...
Chilled Water System (CHWS-1) is an ITER safety cooling system comprised of two independent and segr...
The steam generator in a pressurized water reactor power plant acts as a fission product barrier bet...
A number of Nuclear Power Plants (NPPs) with Pressurized Water Reactors (PWR) in the world have repl...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
The thesis deals with the development and set-up of a specific MELCOR 1.8.6 Fusion Version nodalizat...
The Steam Generator Tube Rupture (SGTR) postulated event constitutes one of the most hazardous safet...
The tube rupture accident is one among the most risk-dominant events at the nuclear power plants. Se...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant ar...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant (N...
After emergency shutdown of high-temperature-gas-cooled reactor, the residual heat of the reactor co...