Development of other small modular nuclear reactor (SMR) technologies in the Republic of Korea

15.3.1 SFR system

15.3.1.1 Phase 1

It has been recognized nationwide that a fast reactor system is one of the most promising nuclear options for electricity generation with an efficient utilization of uranium resources and a reduction of the radioactive waste from NPPs. In response to this recognition, the SFR technology development efforts in Korea commenced in June 1992 with the Korea Atomic Energy Commission’s approval of a national mid — and long-term nuclear R&D program on an SFR with the objective of developing basic key technologies for fast reactors which can meet the goals of a sustainability, safety and economic competitiveness.

At the early stages of its development, the research efforts focused on basic R&D on core neutronics, thermal hydraulics and sodium technology, with the aim to enhance the basic liquid metal-cooled reactor (LMR) technology capabilities. Since 1977, the basic key technology development for an SFR has been continued, and the design concepts of KALIMER-150 and KALIMER-600 have been successfully achieved. In 2008, the Korea Atomic Energy Commission (KAEC) approved a long­term advanced SFR R&D plan which aims at the construction of an advanced SFR prototype plant by 2028 in association with the pyroprocess technology development. The SFR R&D program is shown in Figure 15.3. To support this R&D plan, KAERI has been focusing on the development of an advanced design concept of a burner reactor that satisfies the future goals of safety, economics, sustainability and proliferation resistance. In addition, R&D activities have been developed to achieve a safe and reliable advanced SFR design, such as large-scale sodium thermal-hydraulic test facilities, a supercritical CO2 Brayton cycle system, an under-sodium viewing technique, metal fuel and a safety analysis code.