KEPCO E&C

SFR

Sodium-cooled Fast Reactor (SFR) is an advanced reactor to comply with the technology goals of the Generation IV nuclear energy system: sustainability, safety, economics and nuclear proliferation resistance.

The R&D for SFR prototype plant (Prototype Generation IV Sodium-cooled Fast Reactor: PGSFR) development has been developed since 2012. The goal of the project is to demonstrate the transmutation of transuranic (TRU) materials recovered from the pressurized water reactor (PWR) spent fuel, and hence the benefits of the integral recycling of all actinides (U and TRU) in a closed fuel cycle to nuclear waste management.

PGSFR is a pool type sodium-cooled fast reactor, as shown in Figure with the rated power of 150 MWe. The heat transport system of PGSFR consists of a primary heat transport system (PHTS), intermediate heat transport systems (IHTSs) and a power conversion system (PCS). The PHTS provides the function of a primary coolant boundary, and the IHTS preserves the safety of the reactor core by constructing a buffer region just in case a sodium-water reaction occurs in the steam generators (SGs). As the main components and piping of the PHTS are installed inside the reactor vessel, there is no possibility of the potential loss of coolant due to any pipe rupture. It is also designed to have ufficient thermal inertia to mitigate the rapid thermal transients during all the anticipated events.

PGSFR has two intermediate loops to deliver the heat generated from the core to the power conversion system, and each loop consists of two intermediate heat exchangers(IHX) and a single steam generator producing super-heated steam.

Four independent loops of the decay heat removal system(DHRS) are installed to remove residual heat from the PHTS during a DBA. The DHRS consists of two passive and two active systems.

The reactor building is designed to accommodate pool type reactor, primary heat transport system and safety-related systems, components and structures and seismic isolators is used in the foundation of the building in order to significantly reduce seismic response of major components in the earthquake event. The containment establishes a final barrier against the uncontrolled release of radioactivity to the environment for a DBA. In addition, the ontainment is designed to maintain structural integrity against a beyond design basis accident such as aircraft impacts and severe accidents.

Major Design Characteristics

Development Status

The PGSFR Development project has been carried out as a part of the government’s nuclear technology development project. Sodium cooled Fast Reactor Development Agency (SFRA) was established to carry out project management and licensing management task for this project. Korea Atomic Energy Research Institute (KAERI) performs NSSS design, nuclear fuel design, and manufacturing technology development, while KEPCO E&C performs BOP system design, and Doosan Heavy Industries & Construction performs the review of manufacturing the major components of PGSFR.

Development Lists