Chinese Fusion Engineering Testing Reactor (CFETR) is a tokamak-type machine and next device in the roadmap for the realization of fusion energy in China, which aims to bridge the gaps between the International Thermonuclear Experimental Reactor (ITER) and the demonstration reactor (DEMO) [1]. The accident sequence starting from loss of vacuum accident (LOVA) is an important issue concerning the performance of CFETR. During LOVA, air will leak into the vacuum vessel (VV) causing fast pressurization of VV. At the same time, the high speed airflow jet will result in migration and re-suspension of the large quantity of tungsten dust produced and deposited in the lower part of plasma chamber, causing possibilities of radioactive dust leakage into the workshop and environment. In order to conduct a comprehensive analysis of the accident sequence, firstly, the airflow characteristics of LOVA should be studied. In this article, a postulated rupture of different section area is assumed due to a failed component at the equatorial port level. The computational fluid dynamic (CFD) modelling of LOVA was conducted by ANSYS CFX. The results show that the break area has significant influences on the characteristics of the airflow. Two swirling airflows are formed in the upper and lower part of the torus. The airflow characteristics are quite different when the LOVA happens during maintenance or during normal operation. A reverse flow occurs when the LOVA happens during normal operation. Yet can not be observed when LOVA occurs during maintenance. The results are the basis to the further safety study of CFETR such as the re-suspension, migration and explosion of dust.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5152-4
PROCEEDINGS PAPER
CFD Modelling of Loss of Vacuum Accident (LOVA) for CFETR
Youyou Xu,
Youyou Xu
Chinese Academy of Sciences, Hefei, China
Search for other works by this author on:
Songlin Liu,
Songlin Liu
Chinese Academy of Sciences, Hefei, China
Search for other works by this author on:
Xiaoman Cheng,
Xiaoman Cheng
Chinese Academy of Sciences, Hefei, China
Search for other works by this author on:
Xuebin Ma
Xuebin Ma
Chinese Academy of Sciences, Hefei, China
Search for other works by this author on:
Youyou Xu
Chinese Academy of Sciences, Hefei, China
Songlin Liu
Chinese Academy of Sciences, Hefei, China
Xiaoman Cheng
Chinese Academy of Sciences, Hefei, China
Xuebin Ma
Chinese Academy of Sciences, Hefei, China
Paper No:
ICONE26-81970, V008T09A032; 9 pages
Published Online:
October 24, 2018
Citation
Xu, Y, Liu, S, Cheng, X, & Ma, X. "CFD Modelling of Loss of Vacuum Accident (LOVA) for CFETR." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance. London, England. July 22–26, 2018. V008T09A032. ASME. https://doi.org/10.1115/ICONE26-81970
Download citation file:
22
Views
Related Proceedings Papers
Related Articles
Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios
ASME J of Nuclear Rad Sci (July,2019)
Special Engineering Problems of TFTR
J. Eng. Power (July,1978)
Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code
ASME J of Nuclear Rad Sci (April,2018)
Related Chapters
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
ASME Section III Division 4 Fusion Energy Devices Code Rules
Companion Guide to the ASME Boiler & Pressure Vessel Codes, Volume 2, Sixth Edition
ASME Section III Division 4 Fusion Energy Devices Code Rules
Online Companion Guide to the ASME Boiler & Pressure Vessel Codes