Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea

Abstract

Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for electricity generation, because it can utilize efficiently uranium resources and reduce radioactive waste. Acknowledging the importance of a fast reactor in a future energy policy, the long-term advanced SFR development plan was authorized by KAEC in 2008 and updated in 2011 which will be carried out toward the construction of an advanced SFR prototype plant by 2028. Based upon the experiences gained during the development of the conceptual designs for KALIMER, KAERI recently developed advanced sodium-cooled fast reactor (SFR) design concepts of TRU burner that can better meet the generation IV technology goals. The current status of nuclear power and SFR design technology development program in Korea will be discussed. The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities.

Development of a Physics-Based Monitoring Algorithm Detecting CO2 Ingress Accidents in a Sodium-Cooled Fast Reactor

“…A sample case study of air-injection tests performed in [31] was considered. The residual by pressure measurement data as a black curve of Figure 7 was compared with the calculated L (green dashed line) at k d (blue dashed line) time.…”

Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMR

“…However, previous studies have focused on the type of accidents involving the release of sodium into the airside of the AHX [3]. However, previous studies have focused on the type of accidents involving the release of sodium into the airside of the AHX [3].…”

“…The PDHRS of the PGSFR comprises two sodium-based independent loops, with a DHX immersed in a hot sodium pool and a natural-draft AHX located in the upper region of the reactor building for each loop. However, previous studies have focused on the type of accidents involving the release of sodium into the airside of the AHX [3]. The occurrence of a sodium-air reaction by leaking, or even by rupturing of the heat exchanger tube, can cause direct interaction between the sodium and air.…”

“…The fluid system design of the UCFR-100 is based on that of the Prototype Gen-IV sodium-cooled fast reactor (PGSFR), with the fluid system comprising a heat transport system and a safety system [3]. In contrast with the employment of various safety-related systems by the pressurized water reactor (PWR), the PGSFR employs only two safety-related systems, namely, a decay heat removal system (DHRS) and a sodium-water reaction pressure relief system.…”