Analysis of a massive air ingress accident of the high temperature gas cooled reactor pebble-bed module (HTR-PM) - 18535
Conference
·
OSTI ID:23032680
- Institute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key laboratory of advanced reactor engineering and safety of Ministry of Education, Beijing, China, 100084 (China)
The 200 MWe high temperature gas cooled reactor-pebble bed module (HTR-PM) is a commercial demonstration power plant, which is now under construction in China. For the safety analysis of the HTR-PM, air ingress is a kind of severe accidents, which should be carefully taken into consideration in the design and safety review processes. The double-ended guillotine break (DEGB) of the horizontal coaxial gas duct is an extremely hypothetical air ingress accident of the HTR-PM. This kind of accident may cause some adverse consequences, such as the fuel temperature increasing, graphite corrosion, structure strength weakening, radioactivity release increasing and so on. This paper simulated the DEGB of the horizontal coaxial gas duct of the HTR-PM by using the system analysis software TINTE. Under the conservative assumptions of this accident, the thermal dynamic and graphite oxidation analyses are given in this paper. The simulation results show that the maximum fuel temperature would not exceed the design limit value and the weight loss ratio of the matrix graphite and bottom reflector are about 5.5% and 7.5%, respectively, at 150 h after the accident occurrence. (authors)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23032680
- Country of Publication:
- United States
- Language:
- English
Similar Records
Study on Water-ingress Accident during the Initial Core and the Running-in Phase of HTR-PM - 18429
The hydrogen behavior analysis in the water-ingress accident of the 250 MW pebble-bed modular high temperature gas-cooled reactor - 18639
Modeling The DLOFC Accident Scenario of HTR-PM Equilibrium Core Using NEAMS Tools
Conference
·
Mon Nov 14 23:00:00 EST 2016
·
OSTI ID:23032636
The hydrogen behavior analysis in the water-ingress accident of the 250 MW pebble-bed modular high temperature gas-cooled reactor - 18639
Conference
·
Mon Nov 14 23:00:00 EST 2016
·
OSTI ID:23032719
Modeling The DLOFC Accident Scenario of HTR-PM Equilibrium Core Using NEAMS Tools
Conference
·
Thu Nov 16 23:00:00 EST 2023
·
OSTI ID:2248076