Abstract:
Safety and availability are prime factors for nuclear power plant operation.
Safe operation requires a well-built backup of safety systems for saving plant
capital cost, environment and the public. The backup system is maintained
with the use of active and passive safety systems in the form of engineered
safety features. Traditionally, active safety systems have been utilized for
counteracting accidental conditions. These systems require proper and timely
operator actions, which is some time misleading. Now a day, passive safety
systems are becoming more popular due to their dependence on forces of
nature for operation and actuation. Passive operations include, under gravity
flow, natural recirculation of fluid and nitrogen gas pressure. For such type of
systems, when certain conditions are met and the passive operation is started
automatically. Therefore, world nuclear community has started using passive
safety systems in the present nuclear power plant technology due to the
simplicity in operation, maintenance and safety enhancement.
This thesis concentrates on the augmentation of passive safety features in
small scale pressurized water reactor design. The research was started with
the study and simulation of a small scale reference power plant. The scope of
simulation
includes
safety
systems
including
necessary
nuclear
and
conventional island. The individual process systems and related electrical
systems are simulated and integrated within the frame work of their
respective instrumentation and control to form a standalone simulated model
for a reference power plant. Using this model, design basis accident has been
modeled and the response of the safety systems together with related
primary systems has been observed. Satisfactory results have been
experienced in this regard.
The research was extended by designing and simulating a passive safety
injection system. This proposed system consists of many passive components
and functions in place of an existing safety injection system for mitigating loss
of coolant accidental condition. The use of proposed passive system has been
suggested only for intermediate type pipe breaks because for small breaks,
the depressurization is slow and only high pressure charging system is utilized
whereas for larger breaks, the depressurization is very fast and low pressure
safety injection system is actuated rapidly. Therefore, in a simulation test run
this proposed system has been tested and verified for intermediate coolant
loss accident. It has been found that the response of the proposed passive
system is satisfactory and it keeps all necessary safety parameters within
range. Through this research, it is concluded that the proposed passive
system could be a potential candidate for handling intermediate type breaks
representing loss of coolant accidents in small scale pressurized water
reactors. For other accidental conditions of the plant like steam generator
tubes rupture and steam line break, the use of conventional way of accidental
management has been suggested.
Keywords: Advance NPP, Passive safety, Analysis, LOCA, Reliability