NUCLEAR TECHNIQUES, Volume. 47, Issue 4, 040603(2024)
Analysis of fission product source term release and decay heat under pressurized water reactor rupture accident
Fig. 1. Nodalization of primary loop system 1. Core, 2. Upper plenum, 3. Broken hot leg, 4,10. Hot leg steam generator shell, 5,11. Cold leg steam generator shell, 6,12. Intermediate leg, 7,13. Cold leg, 8. Downcomer, 9. Unbroken hot leg, 14. Reactor dome
Fig. 2. Nodal division of containment 1. Cavity, 2. Lower compartment, 3. Upper compartment, 4. Annular compartment, 5. External environment
Fig. 7. Mass released from fission product source term in-vessel (a) CORSOR-M model, (b) CORSOR-O model, (c) ORNL-BOOTH model
Fig. 8. Masses released from fission product source terms ex-vessel(a) CORSOR-M model, (b) CORSOR-O model, (c) ORNL-BOOTH model
Fig. 16. Fraction of decay heat generated by the source term over the total decay heat fraction
Fig. 17. Spray-off decay heat of fission product components (a) CORSOR-M model, (b) CORSOR-O model (c) ORNL-BOOTH model
Fig. 18. Spray-on total decay heat of fission products (color online)
|
|
|
|
Get Citation
Copy Citation Text
Xianbao YUAN, Jueqin PENG, Binhang ZHANG, Zhangliang MAO, Haibo TANG, Jingyu WEI, Jianjun ZHOU. Analysis of fission product source term release and decay heat under pressurized water reactor rupture accident[J]. NUCLEAR TECHNIQUES, 2024, 47(4): 040603
Category: Research Articles
Received: Aug. 10, 2023
Accepted: --
Published Online: May. 28, 2024
The Author Email: MAO Zhangliang (毛璋亮)