The life extension of the Phe´nix LMFR involved the inspection of reactor vessel internal structures : among other techniques, a visual inspection was performed of the above core structure, fuel assembly heads and upper components. To make this inspection possible, a partial draining of the main vessel from primary liquid sodium was carried out (sodium at 180°C and argon cover at 150°C). The test program aimed at obtaining further knowledge on the process of wetting of sodium — as pure metal — on Phe´nix Plant assembly heads — made of stainless steel —, as well as on the internal structure weldings, was carried out from November 1998 to January 1999. The main results were as follows: • the sodium meniscus measured during sodium lowering against the non-wet vertical structures reaches 10 mm in height. On wetted structures, it reaches only 5.3 mm. • when sodium level decreases, the process if very regular. However, re-flooding is carried out in stages. • a difference of 0.2 mm between two heads altitudes is enough to observe successively each of the heads. • the quality of sodium does not modify the wetting process (in the range of cold trap temperature : 110–140°C). • the influence of lighting is important. • the visibility limit of emerging electro-eroded cracks (from 0.17 to 1.0 mm) is at 0.20 mm. • the visibility of a horizontal welding, machined or not, is good when the lighting is sufficient. • the superficial flow of sodium only modifies the wetting process for the closest heads. A final test allowed to observe that the global inclination of the assembly head mock-up does not modify the wetting process. These experimental results were part of the feasibility demonstration of the visual inspection within the actual Phe´nix Plant that was undertaken in 2001.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3595-2
PROCEEDINGS PAPER
Emersion Testing of Phe´nix Reactor Components From Liquid Sodium
F. Baque´
CEA/DEN/CAD/DER, St Paul lez Durance, France
L. Martin
CEA/DEN/Phenix, Bagnols sur Ceze, France
Paper No:
ICONE10-22083, pp. 205-210; 6 pages
Published Online:
March 4, 2009
Citation
Baque´, F, & Martin, L. "Emersion Testing of Phe´nix Reactor Components From Liquid Sodium." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 1. Arlington, Virginia, USA. April 14–18, 2002. pp. 205-210. ASME. https://doi.org/10.1115/ICONE10-22083
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
J. Eng. Gas Turbines Power (May,2011)
Interactions Between Molten Sodium and Standard Pipe Insulation
ASME J of Nuclear Rad Sci (July,2024)
Probability of Fracture and Life Extension Estimate of the High-Flux Isotope Reactor Vessel
J. Pressure Vessel Technol (August,1998)
Related Chapters
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
Development of Nuclear Boiler and Pressure Vessels in Taiwan
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 & Pressure Vessel Codes, Volume 1 Sixth Edition