Smart first wall materials for intrinsic safety of a fusion power plant
Creators
- 1. Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung, 52425 Jülich (Germany)
- 2. Department of Applied Physics, Ghent University, B-9000 Ghent (Belgium)
- 3. CCFE, United Kingdom Atomic Energy Authority, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB (United Kingdom)
- 4. School of Materials Science and Engineering, Hefei University of Technology, Hefei 230009 (China)
- 5. Institute for Materials Applications in Mechanical Engineering, RWTH Aachen University (Germany)
Description
The first wall armor of a DEMOnstration fusion power plant (DEMO) is planned to be built from tungsten. However, in case of loss-of-coolant accident with air ingress, the temperature of the first wall may exceed 1000 °C due to nuclear decay heat. At such temperatures, tungsten forms volatile radioactive oxides, which may be mobilized into the environment at a rate of 10–600 kg per hour. Advanced "smart" tungsten alloys adjust their properties to the environment: during the plasma operation, preferential sputtering will form almost pure tungsten surface facing the plasma. In case of an accident, the remaining alloying elements form a protective layer, preventing tungsten mobilization. The new smart alloys contain tungsten (W), chromium (Cr) and yttrium (Y). The first bulk smart alloys produced using field-assisted sintering technique, revealed excellent oxidation resistance for a timescale of 10–20 hours. W-Cr-Y systems underwent combined plasma and oxidation test. During plasma exposure, smart alloys demonstrated nearly the same mass loss as the reference pure tungsten samples. Subsequent oxidation confirmed superior oxidation resistance of new alloys compared to the former W-Cr-Ti systems. Experiments attaining oxidation times and plasma fluence required for DEMO, are started. First results show necessity in further improvement of W-Cr-Y alloys.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2018.04.028Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2018.04.028;
- PII
- S0920379618303168;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 136
- Journal Issue
- Part B
- Journal Page Range
- p. 878-882
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51011944
- Subject category
- S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- AFTER-HEAT; CHROMIUM; COMPARATIVE EVALUATIONS; FIRST WALL; LAYERS; LOSS OF COOLANT; MASS TRANSFER; NUCLEAR DECAY; OXIDATION; PLASMA; SAFETY; SURFACES; THERMONUCLEAR POWER PLANTS; TUNGSTEN; TUNGSTEN ALLOYS; YTTRIUM
- Descriptors DEC
- ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; DECAY; ELEMENTS; EVALUATION; METALS; POWER PLANTS; REACTOR ACCIDENTS; REFRACTORY METALS; THERMAL POWER PLANTS; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS
Optional Information
- Notes
- © 2018 The Authors. Published by Elsevier B.V. All rights reserved.