Radiation Damage Limitations in the Design of the Wisconsin Tokamak Fusion Reactor
- 1 April 1974
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 22 (1), 20-35
- https://doi.org/10.13182/nt74-a16271
Abstract
A detailed analysis of the radiation damage problems to be expected in a specific D-T fueled fusion reactor has been conducted. The system examined is the 5000-MW(th) University of Wisconsin Tokamak reactor (UWMAK), which is constructed of 20% cold-worked Type-316 stainless steel and operated at a maximum temperature of 500°C and a neutron wall loading of 1.25 MW/m2. The major radiation damage problem appears to be the loss in ductility; that is, the uniform elongation of the Type-316 stainless steel in the UWMAK-I first wall may fall to 2, respectively.Keywords
This publication has 15 references indexed in Scilit:
- Tensile properties of annealed type 316 stainless steel after EBR-II irradiationJournal of Nuclear Materials, 1973
- 20. Tensile and creep behaviour of cold worked type 316 stainless steel after EBR-II irradiationPublished by Thomas Telford Ltd. ,1973
- Blistering of polycrystalline and monocrystalline niobiumRadiation Effects, 1973
- Effect of channeling and irradiation temperature on the morphology of blisters in niobiumApplied Physics Letters, 1972
- The rate theory of swelling due to void growth in irradiated metalsJournal of Nuclear Materials, 1972
- Fast neutron irradiation induced resistivity in metalsPhysica Status Solidi (a), 1972
- On the theory of void formation during irradiationRadiation Effects, 1972
- Voids in Irradiated Stainless SteelNature, 1967
- Production and Recovery of Electron-Induced Radiation Damage in a Number of MetalsPhysical Review B, 1962
- Sputtering experiments in the high energy regionNuclear Instruments and Methods, 1961