Helium purification and helium auxiliary system is one of important systems guaranteeing the safe operation of high-temperature gas-cooled reactor. In this system, wire mesh mist eliminator is one of the key components and used to separate waste water containing tritium, and remove moisture after reactor accident. Base on the ideal fluid model and packing pad model developing by Carpenter, A calculation model is presented for separation efficiency of mist eliminator. The calculation program “SEP-WMME” is developed based on the model. The calculation results fit well with experiment results. Theoretic analysis is carried out for the mist eliminator of HTR-PM helium purification system engineering validation test loop. The analysis shows the inlet velocity is an important parameter for mist eliminator. When the inlet velocity is above 3.0m/s, high separation efficiency will be obtained.
Skip Nav Destination
2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5579-9
PROCEEDINGS PAPER
Theoretic Analysis on Separation Efficiency of Wire Mesh Mist Eliminator of High-Temperature Gas-Cooled Reactor Helium Purification and Auxiliary System
Huaqiang Yin,
Huaqiang Yin
Tsinghua University, Beijing, China
Search for other works by this author on:
Xingtuan Yang,
Xingtuan Yang
Tsinghua University, Beijing, China
Search for other works by this author on:
Xuedong He
Xuedong He
Tsinghua University, Beijing, China
Search for other works by this author on:
Huaqiang Yin
Tsinghua University, Beijing, China
Lei Hao
Tsinghua University, Beijing, China
Xingtuan Yang
Tsinghua University, Beijing, China
Xuedong He
Tsinghua University, Beijing, China
Paper No:
ICONE21-15417, V002T03A015; 6 pages
Published Online:
February 7, 2014
Citation
Yin, H, Hao, L, Yang, X, & He, X. "Theoretic Analysis on Separation Efficiency of Wire Mesh Mist Eliminator of High-Temperature Gas-Cooled Reactor Helium Purification and Auxiliary System." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors. Chengdu, China. July 29–August 2, 2013. V002T03A015. ASME. https://doi.org/10.1115/ICONE21-15417
Download citation file:
15
Views
Related Proceedings Papers
Related Articles
Experimental Investigation on Additively Manufactured Transpiration and Film Cooling Structures
J. Turbomach (March,2019)
Brush Seal Leakage Performance With Gaseous Working Fluids at Static and Low Rotor Speed Conditions
J. Eng. Gas Turbines Power (April,1993)
Hydrate-Based Carbon Capture Process: Assessment of Various Packed Bed Systems for Boosted Kinetics of Hydrate Formation
J. Energy Resour. Technol (March,2021)
Related Chapters
Application of Probabilistic Methods for the Evaluation of Deterministic Deviations from Technical Specifications (PSAM-0277)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
The Thermo —Mechanical Analysis of Mechanical Packing (SEAL), Using Finite Element Method (FEM) — Results and Conclusions
International Conference on Mechanical Engineering and Technology (ICMET-London 2011)