In a nuclear accident, radioactive release source term is the critical factor of nuclear emergency response and accident assessment. The modelling of source inversion based on variational data assimilation (VAR) is capable of balancing the environmental radioactive monitoring data to obtain the global optimal source term. But it could be influenced by the discrepancy between predictions of the atmospheric dispersion model and observations, which is defined as the dispersion model error in this study. In order to reduce this influence, the VAR with the dispersion model error (DME-VAR) is proposed. In the DME-VAR, the dispersion model error is quantified by the error coefficients at every monitoring station. These error coefficients and the release source term are estimated at the same time. For limiting the runtime, the DME-VAR program supports parallel processing. Two sets of wind tunnel experiment data for a typical Chinese nuclear power plant site are used to validate and evaluated the performance of the DME-VAR. The results demonstrate that the DME-VAR effectively estimates the error coefficients, and outperforms the VAR in both release rate estimation and radioactive contamination predicting. Moreover, the runtimes of these verification experiments are all reasonable, even for the application in the nuclear emergency response.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5146-3
PROCEEDINGS PAPER
Research on Source Inversion for Nuclear Accidents Based on Variational Data Assimilation With the Dispersion Model Error Available to Purchase
Yun Liu,
Yun Liu
China Nuclear Power Engineering Co., Ltd., Beijing, China
Search for other works by this author on:
Xinjian Liu,
Xinjian Liu
China Nuclear Power Engineering Co., Ltd., Beijing, China
Search for other works by this author on:
Sheng Fang,
Sheng Fang
Tsinghua University, Beijing, China
Search for other works by this author on:
Yawei Mao,
Yawei Mao
China Nuclear Power Engineering Co., Ltd., Beijing, China
Search for other works by this author on:
Jingyuan Qu
Jingyuan Qu
Tsinghua University, Beijing, China
Search for other works by this author on:
Yun Liu
China Nuclear Power Engineering Co., Ltd., Beijing, China
Xinjian Liu
China Nuclear Power Engineering Co., Ltd., Beijing, China
Hong Li
Tsinghua University, Beijing, China
Sheng Fang
Tsinghua University, Beijing, China
Yawei Mao
China Nuclear Power Engineering Co., Ltd., Beijing, China
Jingyuan Qu
Tsinghua University, Beijing, China
Paper No:
ICONE26-81094, V004T06A005; 7 pages
Published Online:
October 24, 2018
Citation
Liu, Y, Liu, X, Li, H, Fang, S, Mao, Y, & Qu, J. "Research on Source Inversion for Nuclear Accidents Based on Variational Data Assimilation With the Dispersion Model Error." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation. London, England. July 22–26, 2018. V004T06A005. ASME. https://doi.org/10.1115/ICONE26-81094
Download citation file:
27
Views
Related Proceedings Papers
Related Articles
Efficient Parallel Simulation of Direct Methanol Fuel Cell
Models
J. Fuel Cell Sci. Technol (May,2005)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Integrated Human Reliability Analysis Methodology for External Control Room Emergency Response Scenarios: Application to Modeling FLEX Human Actions in Nuclear Power Plants
ASME J. Risk Uncertainty Part B (January,0001)
Related Chapters
A PSA Update to Reflect Procedural Changes (PSAM-0217)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Link between Level 2 PSA and Off-Site Emergency Preparedness (PSAM-0363)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)