Two phase flow stability in the HTR-10 steam generator
Creators
- 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology
Description
A 10 MW High Temperature Gas Cooled Reactor (HTR-10) designed by the Institute of Nuclear Energy Technology (INET) is now being constructed. The steam generator (SG) in the HTR-10 is one of the most important components for reactor safety. The thermal-hydraulic performance of the SG was investigated. A full scale HTR-10 Steam Generator Two Tube Engineering Model Test Facility (SGTM-10) was installed and tested at INET. The author describes the SGTM-10 thermal hydraulic experimental system in detail. The SGTM-10 simulates the actual thermal and structural parameters of the HTR-10. The SGTM-10 includes three separated loops: the primary helium loop, the secondary water loop, and the tertiary cooling water loop. Two parallel tubes are arranged in the test assembly. The main experimental equipment is shown. Experimental results are given illustrating the effects of the outlet pressures, the heating power, and the inlet subcooling
Additional details
Publishing Information
- Journal Title
- Tsinghua Science and Technology
- Journal Volume
- 6
- Journal Issue
- 1
- Journal Page Range
- p. 75-79
- ISSN
- 1007-0214
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 33027509
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; EXPERIMENTAL DATA; HTR-10 REACTOR; ONCE-THROUGH COOLING SYSTEMS; STABILITY; STEAM GENERATORS; TEST FACILITIES; TWO-PHASE FLOW
- Descriptors DEC
- BOILERS; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INFORMATION; NUMERICAL DATA; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES; TEST REACTORS; VAPOR GENERATORS