Mitsubishi Heavy Industries, Ltd. (MHI) completed replacement work of upper reactor internals (UCI) and lower reactor internals (LCI) of the pressurized water reactor in Shikoku Electric Power Company’s Ikata Unit No.1 by “the all-in-one-piece extraction method” introduced in the document of [ICONE14-89233]. In the pressurized water reactor (PWR) plant, the UCI are usually removed from the reactor vessel (RV) independently and reinstalled into the RV again every refueling outage. The LCI are independently able to be removed from the RV and reinstalled again during in-service inspection, too. In the boiling water reactor (BWR) plant, there are several cases of replacing BWR shrouds by cutting small and containing in a container. But no replacement of all reactor internals (CI) for the PWR, in one piece without splitting or cutting, has been reported. The purpose of this paper is to introduce the key points about the design and manufacture of the storage cask for old reactor internals in the replacement work by “the all-in-one-piece extraction method”.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
Design and Manufacture of the Storage Cask for the Old Reactor Internals
Yasuhiro Tomiita
Yasuhiro Tomiita
Mitsubishi Heavy Industries, Ltd., Kobe, Japan
Search for other works by this author on:
Yasuhiro Tomiita
Mitsubishi Heavy Industries, Ltd., Kobe, Japan
Paper No:
ICONE14-89838, pp. 311-315; 5 pages
Published Online:
September 17, 2008
Citation
Tomiita, Y. "Design and Manufacture of the Storage Cask for the Old Reactor Internals." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 311-315. ASME. https://doi.org/10.1115/ICONE14-89838
Download citation file:
9
Views
Related Proceedings Papers
Related Articles
Cyclic Crack Growth Behavior of Reactor Pressure Vessel Steels in Light Water Reactor Environments
J. Eng. Mater. Technol (January,1986)
A Risk-Informed Methodology for ASME Section XI, Appendix G
J. Pressure Vessel Technol (June,2012)
In Memoriam: Jan Kysela
ASME J of Nuclear Rad Sci (April,2016)
Related Chapters
Czech and Slovakian Codes
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Subsection NG — Core Support Structures
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition
Subsection NG—Core Support Structures
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition