Light water reactors in Japan are expected to restart sequentially after given permission in condition to meet the new regulatory requirements. Since several safety related systems were added to the plants through the process of the new regulatory requirements, the numbers of components to be inspected, which is already a large amount, will increase even more after the restart in Japan. Effective measure will be required to command maintenance activities by reasonably assigning limited resource. The authors have planned a research project aiming optimization of maintenance considering influence of fluid leakage behavior with pipe failure, mainly targeting less-safety related piping and components. The experimental facility which has the ability to evaluate the fluid leakage behavior with pipe failure was constructed. By using this facility, it is able to conduct the test of the water jet, the flashing and the steam flow leaked from various flaw geometries of the piping.
Skip Nav Destination
ASME 2017 Pressure Vessels and Piping Conference
July 16–20, 2017
Waikoloa, Hawaii, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5800-4
PROCEEDINGS PAPER
Study on Diffusion Area of Fluid Leakage With Pipe Failure
Shun Watanabe,
Shun Watanabe
Central Research Institute of Electric Power Industry, Yokosuka, Japan
Search for other works by this author on:
Kimitoshi Yoneda
Kimitoshi Yoneda
Central Research Institute of Electric Power Industry, Yokosuka, Japan
Search for other works by this author on:
Shun Watanabe
Central Research Institute of Electric Power Industry, Yokosuka, Japan
Kimitoshi Yoneda
Central Research Institute of Electric Power Industry, Yokosuka, Japan
Paper No:
PVP2017-65193, V06BT06A014; 6 pages
Published Online:
October 26, 2017
Citation
Watanabe, S, & Yoneda, K. "Study on Diffusion Area of Fluid Leakage With Pipe Failure." Proceedings of the ASME 2017 Pressure Vessels and Piping Conference. Volume 6B: Materials and Fabrication. Waikoloa, Hawaii, USA. July 16–20, 2017. V06BT06A014. ASME. https://doi.org/10.1115/PVP2017-65193
Download citation file:
17
Views
Related Proceedings Papers
Related Articles
Rupture Hardware Minimization in Pressurized Water Reactor
Piping
J. Pressure Vessel Technol (February,1989)
The Plant Feature and Performance of Double MS (Modular Simplified and Medium Small Reactor)
J. Eng. Gas Turbines Power (January,2010)
Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
ASME J of Nuclear Rad Sci (April,2018)
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Fourth Edition