Sodium-CO<sub>2</sub> Interaction in a Supercritical CO<sub>2</sub> Power Conversion System Coupled with a Sodium Fast Reactor

Eoh, Jaehyuk; No, Hee Cheon; Yoo, Yong-Hwan; Kim, Seong-O

doi:10.13182/nt11-a11541

Cited by 21 publications

(1 citation statement)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…To quantify the reaction rate for various sodium temperatures and determine the detailed kinetic parameters coupled with a mass diffusion process, a two zone model was proposed and experimental work on a surface reaction test was carried to decide the value of the / values of Figure 20. From the test results, it was found that the reaction kinetics over a sodium temperature range of 300 ∘ C to 500 ∘ C depends heavily on temperature but is not sensitive to a mass transfer effect, and it was also found that the two zone model with a 460 ∘ C threshold temperature is valid for the temperature range of a sodium fast reactor [8]. Furthermore, we need to investigate the ingress of a CO/CO 2 mixture gas into the primary coolant path and the resulting induction of a potential CO 2 void transport to the reactor core as a critical issue.…”

Section: S-co 2 Braytonmentioning

confidence: 99%

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

Kim

Lee

et al. 2013

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

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.

show abstract

Section: S-co 2 Braytonmentioning

confidence: 99%