Nuclear Reactor Safety Systems Availability Upgrading Analysis (CROSBI ID 465216)
Prilog sa skupa u zborniku | izvorni znanstveni rad
Podaci o odgovornosti
Mikuličić, Vladimir ; Šimić, Zdenko
engleski
Nuclear Reactor Safety Systems Availability Upgrading Analysis
The analysis evaluates the consequences of the removal of the autoclosure interlock (ACI) on the Residual Heat Removal System (RHRS) suction/isolation valves at the nuclear power plant. The deletion of the RHRS ACI is in part based on a probabilistic safety analysis (PSA) which justifies the removal based on a criterion of increased availability and reliability. Three different areas are to be examined in PSA: the likelihood of an interfacing system LOCA, RHRS unavailability, and low temperature overpressurisation control. The paper emphasises particularly the RHRS unavailability and the likelihood of an interfacing system LOCA evaluation utilising the current control circuitry configuration and then with the proposed modification to the control circuitry. key words: autoclosure interlock, residual heat removal system, probabilistic safety analysis
autoclosure interlock; residual heat removal system; probabilistic safety analysis
nije evidentirano
nije evidentirano
nije evidentirano
nije evidentirano
nije evidentirano
nije evidentirano
Podaci o prilogu
497-503-x.
1996.
objavljeno
Podaci o matičnoj publikaciji
Nuclear Option in Countries with Small and Medium Electricity Grid
Knapp, Vladimir ; Čavlina, Nikola
Hrvatsko nuklearno društvo
Podaci o skupu
International Conference: Nuclear Option in Countries with Small and Medium Electricity Grid
poster
07.10.1996-09.10.1996
Opatija, Hrvatska