Operation Experience of LBE Loop: HELIOS

Conference · Sat Jul 01 04:00:00 EDT 2006

OSTI ID:21021084

Seung Ho, Jeong; Chi Bum, Bahn; Seung Hee, Chang; Young Jin, Oh; Won Chang, Nam; Kyung Ha, Ryu; Hyo On, Nam; Jun, Lim; Tai Hyun, Lee; Seung Gi, Lee; Na Young, Lee; Il Soon, Hwang ^[1]

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1. Nuclear Transmutation Energy Research Center of Korea (NUTRECK), Seoul National University San 561-, Sillim-dong, Gwanak-gu, Seoul 151-742 (Korea, Republic of)

An LBE (lead-bismuth eutectic) coolant loop, named as HELIOS (Heavy Eutectic liquid metal Loop for Investigation of Operability and Safety of PEACER), has been designed by thermal-hydraulic scaling of the PEACER-300MW{sub e} (Proliferation-resistant, Environment-friendly, Accident-tolerant, Continuable and Economical Reactor). HELIOS is consisted of an electrically-heated core at its bottom and a heat exchanger at its top with their mean elevation difference of 8 meter, closely matching with that of PEACER. Natural circulation experiment and material test are principal goals of HELIOS operation. About 2 metric ton of LBE is circulated by a centrifugal pump at a rate up to 76 liter/min through HELIOS having a total 12 meter height. A material test bypass was installed to perform LBE corrosion experiments in continuous operation conditions at temperature and flow velocity higher than nominal values. During the initial start-up test, there was an accidental cooling water leak into LBE at around 250 deg C, but without any consequences. A small LBE leak occurred through a crack in a bellows for connecting storage tank to the main loop, apparently due to excessive stress arisen from faulty installation, however, there was no significant safety hazard or chemical reaction with environment. Many practical difficulties arouse with sensors for pressure measurement, level control in sump pump tank. LBE loop operation experiences are summarized herein. Upon the sensor calibrations, HELIOS will be utilized to examine the materials durability and natural circulation capability of PEACER-300. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21021084
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BISMUTH
CENTRIFUGAL PUMPS
COOLANT LOOPS
CORROSION
EUTECTICS
FASTENING
HEAT EXCHANGERS
LIQUID METALS
NATURAL CONVECTION
OPERATION
PRESSURE MEASUREMENT
SAFETY
TANKS
THERMAL HYDRAULICS