Thermal hydraulic transient analysis of the HTR-10
The HTR-10 is the first high temperature gas-cooled test module reactor built in China. In the accident analysis, typical design basis accident and beyond design basis accident (BDBA), including the reactivity accident, the loss of external power ATWS, the air ingress accident and water ingress acci...
Gespeichert in:
Veröffentlicht in: | Nuclear engineering and design 2002-10, Vol.218 (1), p.65-80 |
---|---|
Hauptverfasser: | , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
Zusammenfassung: | The HTR-10 is the first high temperature gas-cooled test module reactor built in China. In the accident analysis, typical design basis accident and beyond design basis accident (BDBA), including the reactivity accident, the loss of external power ATWS, the air ingress accident and water ingress accident into the primary system are selected and detailed analyzed. The results show that the HTR-10 has inherent safety properties. The maximum fuel element temperature will not exceed the limit value 1230
°C. The total amount of graphite corrosion maintains no more than 320 kg, the exposure ratio of first coated particles is less than 2.4% in the BDBA. The released radioactivity is limited at a low level and the ability of fuel particles to retain fission products is not corrupted. Even the consequence of the severest hypothetical accident has no safety danger to the reactor. The reactor can shut itself down via its negative temperature coefficient of reactivity in heat-up conditions. |
---|---|
ISSN: | 0029-5493 1872-759X |
DOI: | 10.1016/S0029-5493(02)00199-1 |