| Abstrak/Abstract |
The Floating Nuclear Power Plant KLT-40S is a Small Modular Reactor (SMR) developed by Afrikantov OKB Mechanical Engineering, Russia. In operating KLT-40S, safety standards must be ensured during steady and transient conditions with a safety parameter of MDNBR, especially in accident conditions such as loss-of-flow accident (LOFA). Thus, The nuclear reactor safety systems under all operating conditions must be analyzed using various form of thermal hydraulic analysis. One of the form of thermal hydraulic analysis is subchannel analysis. The subchannel code SUBCHANFLOW is used in subchannel analysis on KLT-40S fuel assembly (FA). Simulations are conducted in steady- state and transient LOFA trip 1 pump to 4 pumps with nuclear power reduction/SCRAM if needed. The parametric survey is conducted by varying the pitch width and active height of the FA. MDNBR value at steady-state is 3.4407. MDNBR on LOFA trip 1 until 3 pump are at the reactor safety margin; 3.2555, 1.952, and 1.3713. However, on LOFA trip 4 pumps, the MDNBR value is 0.99785. Starting SCRAM early when the coolant mass flow rate hits 87% of its original value could increase MDNBR; to 3.3476. |
