Performance tests of helium circulator under abnormal cooling conditions - 18523
Creators
- 1. Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing, China, 10084 (China)
Description
Helium circulator is one of the key equipment of High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM) and the unique rotating equipment of primary loop. It transports heat generated by fission reactions from reactor core to steam generator by forcing helium circulating in primary loop. As the study on the characteristics of helium circulator in HTGR was limited and the advanced designs integrated with many new technologies, a prototype of helium circulator was manufactured. It was supported by Active Magnetic Bearings (AMBs), and was assembled in a pressure vessel. The prototype was tested in Engineering Test Facility - Helium Circulator (ETF-HC), which is a full scale, rated flow rate and power, engineering test loop. Although performance tests under normal operation condition were successfully fulfilled, the complete features and performance still need further verification, especially for abnormal cooling conditions. Thus performance tests under abnormal cooling operation conditions were carried out. Tests such as temporary coolant loss of motor and AMBs cooler and abnormal high-temperature cooling water condition were fulfilled. All performance tests results showed that helium circulator met the entire requirement of HTR-PM plant under abnormal cooling conditions and validated its safety and reliability. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 3 p.
Conference
- Title
- International Topical Meeting on High Temperature Reactor Technology
- Acronym
- HTR 2016
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52073037
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; COOLING; DESIGN; FLOW RATE; HEAT; HEAT EXCHANGERS; HELIUM; HTGR TYPE REACTORS; MAGNETIC BEARINGS; PERFORMANCE; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; RELIABILITY; STEADY-STATE CONDITIONS; STEAM GENERATORS; TEST FACILITIES; VERIFICATION
- Descriptors DEC
- BEARINGS; BOILERS; CONTAINERS; COOLING SYSTEMS; ELEMENTS; ENERGY; ENERGY SYSTEMS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; NONMETALS; OPERATION; RARE GASES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTORS; SAFETY; VAPOR GENERATORS
Optional Information
- Notes
- 7 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)