DocumentCode :
1454696
Title :
Long-Term Operation and Basic Corrosion Test in an Experimental Loop for Liquid Breeder in Korea
Author :
Yoon, Jae Sung ; Kim, Suk-Kwon ; Jung, Yang Il ; Lee, Dong Won ; Cho, Seungyon
Author_Institution :
Korea Atomic Energy Res. Inst., Daejeon, South Korea
Volume :
40
Issue :
3
fYear :
2012
fDate :
3/1/2012 12:00:00 AM
Firstpage :
777
Lastpage :
781
Abstract :
Korea has developed a liquid breeder blanket and participated in the test blanket module (TBM) program within the international thermonuclear experimental reactor group with a helium-cooled molten lithium (Li) concept. Based on this concept, helium and liquid Li were used as a coolant and breeder, respectively. Additionally, ferritic-martensitic steel (FMS) was considered as a structural material. However, according to our strategy for developing a liquid breeder TBM and its more relevant DEMO concept, not only liquid Li breeders, but also lead-Li (PbLi) breeders were considered. An experimental loop for a liquid breeder (ELLI) was constructed for the purpose of validating the design and fabrication of our electromagnetic (EM) pump; testing the effects of the magneto-hydro-dynamics; and investigating the compatibility of PbLi using structural materials such as FMS. In the ELLI, Pb-15.7Li, where Li is 15.7 at % (called PbLi hereafter), is used as the breeding material, and the EM pump circulates it through the loop. The maximum operating pressure and temperature in the loop are 0.5 MPa and 550 °C, respectively. In this paper, performance tests with the EM pump were carried out. During the three separate experiments, the EM pump was operated for 250 h with a speed of 0.16 m/s for corrosion tests. For a material of corrosion test, tubular-type specimens and cylindrical-type specimens were fabricated and installed in three test pots of the loop. After installing the specimens into the loop, the corrosion test was performed while the EM pump was operating with a 0.16 m/s flow rate at 340 °C for 250 h.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactor fuel; plasma toroidal confinement; DEMO concept; Korea; basic corrosion test; cylindrical-type specimens; electromagnetic pump; ferritic-martensitic steel; helium-cooled molten lithium; international thermonuclear experimental reactor group; lead-Li breeders; liquid Li breeders; liquid breeder blanket; long-term operation; loop test pots; magneto-hydro-dynamic effects; maximum operating pressure; maximum operating temperature; pressure 0.5 MPa; structural material; temperature 550 degC; test blanket module program; Corrosion; Fusion reactors; Inductors; Lithium; Magnetic liquids; Steel; Corrosion; electromagnetic (EM) pump; international thermonuclear experimental reactor (ITER); liquid breeder; test blanket module (TBM);
fLanguage :
English
Journal_Title :
Plasma Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0093-3813
Type :
jour
DOI :
10.1109/TPS.2012.2184775
Filename :
6156462
Link To Document :
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