Published May 1997
| Version v1
Journal article
Thermal fatigue tests on disruption-damaged first-wall components
Creators
- 1. Politecnico di Torino (Italy). Dipartimento di Energetica
- 2. Joint Research Centre, Institute for Advanced Materials, I-21020 Ispra (Italy)
- 3. Joint Research Centre, Institute for Advanced Materials, Petten (Netherlands)
- 4. The NET Team, Boltzmannstrasse 2, D-85748 Garching bei Muenchen (Germany)
Description
The possible synergistic effects between the thermal damage of a plasma disruption and the thermal fatigue lifetime of a bare first wall are investigated. The heat flux of a typical plasma disruption was applied on three stainless steel first-wall mock-ups by means of an electron beam gun. Then these damaged components were subjected to a thermal fatigue test to study the possible propagation of the cracks nucleated during resolidification. After 50000 thermal fatigue cycles at relevant heat load conditions, no propagation was observed in spite of the high numerically computed stress level. (orig.)
Additional details
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 36
- Journal Issue
- 2-3
- Journal Page Range
- p. 367-376.
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 19. symposium on fusion technology (SOFT-19).
- Dates
- 16-20 Sep 1996.
- Place
- Lisbon (Portugal).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 28066398
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; FIRST WALL; STAINLESS STEELS; THERMAL FATIGUE; THERMAL TESTING; WALL EFFECTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; FATIGUE; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; NONDESTRUCTIVE TESTING; STEELS; TESTING; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS