Non-linear assessment of critical failure modes in the first wall of the European TBM
Creators
- 1. Karlsruhe Institute of Technology (KIT), Institute for Applied Materials, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)
- 2. Fusion for Energy (F4E), ITER Delivery Department, TBMs & Materials Development, C/Josep Pla. 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)
Description
The assessment of the different components of the Helium Cooled Pebble Bed (HCPB) and Helium Cooled Lithium Lead (HCLL) Test Blanket Modules (TBMs) based on elastic FE analyses has been performed considering main failure modes and respective structural design criteria. This study has been carried out for the operation at full power and for the so-called Approach 2 cooling that is set up at reduced heat extraction capability for compliance with temperature targets to be relevant to DEMOnstration power plant blanket system. Consequently this situation is the worst condition in terms of cooling performance as a result it reveals that many locations in the First Wall (FW) become critical in the sense that certain criteria are not fulfilled, particularly those for immediate plastic flow localization, progressive deformation (ratcheting) and creep-fatigue interaction. Of course one can better reach code compliance by improving the cooling performance (so called Approach 1) but it will degrade the DEMO relevancy. The critical failure modes are re-assessed performing non-linear analysis using an elasto-viscoplatic model, particularly developed for RAFM steels such as the structural material EUROFER97 by Aktaa & Schmitt, and considering the appropriate design criteria of the inelastic route of RCC-MRx and SDC-IC. Despite the conservatism in these criteria, the results show all-clear signal with respect to immediate plastic flow localization and at least much smaller breaches of the limits with respect to the other failure modes. Reporting details and results of the non-linear failure assessments demonstrates their potential and capability in supporting specific and efficient improvements to the design of highly loaded components. The conservatism in the considered design criteria and ways for its reduction are discussed in addition.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2017.11.032Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2017.11.032;
- PII
- S092037961730947X;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 128
- Journal Page Range
- p. 223-230
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51012065
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DEMONSTRATION PLANTS; FATIGUE; FIRST WALL; GAS COOLED REACTORS; HEAT EXTRACTION; HELIUM; INTERACTIONS; LEAD; LIQUID METAL COOLED REACTORS; LITHIUM; STEELS
- Descriptors DEC
- ALKALI METALS; ALLOYS; CARBON ADDITIONS; ELEMENTS; FLUIDS; GASES; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; METALS; NONMETALS; RARE GASES; REACTORS; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- © 2018 Karlsruhe Institute of Technology (KIT). Published by Elsevier B.V. All rights reserved.