Published 1998 | Version v1
Book

Re-weldability tests of irradiated Inconel 625 by TIG welding method

  • 1. JAERI, Narita, Oarai, Higashi-ibaradki (Japan). Oarai Research Establishment
  • 2. Tokyo Univ. (Japan)
  • 3. Japan Power Engineering and Inspection Corp., Nishihara, Tarasaki (Japan)
  • 4. ITER Joint Work Site, Garching (Germany)

Description

Inconel 625 is one of the possible materials for the vacuum vessel (VV) and for the in-vessel components of fusion reactors where high strength and high electrical resistance are required. In particular, Inconel 625 is used for the VV of JET and for flexible branch pipe lines in the ITER design. One of the most important issues for their applications is its re-weldability between un-irradiated and irradiated materials. This has a large impact on the design of in-vessel components. In this study, re-weldability of un-irradiated and/or irradiated Inconel 625 that has been welded by the tungsten inert gas (TIG) welding process has been examined, and effect of helium generation amount on mechanical properties of the weld joint has been discussed. (authors)

Part of:
Fusion technology 1998

Additional details

Publishing Information

Publisher
Association Euratom-CEA Cadarache
Imprint Place
Saint-Paul-Lez-Durance (France)
Imprint Title
Fusion technology 1998
Imprint Pagination
(v.1-2) 1744 p.
Journal Page Range
p. 1297-1300

Conference

Title
20. symposium on fusion technology
Dates
7-11 Sep 1998
Place
Marseille (France)

Optional Information

Notes
11 refs.