References
- H. YAMADA et al., “Japanese Endeavors to Establish Technological Bases for DEMO,” Fusion Eng. Des., 109–111, 1318 (2016); https://doi.org/10.1016/j.fusengdes.2015.12.035.
- M. KIKUCHI, “Steady State Tokamak Reactor Based on the Bootstrap Current,” Nucl. Fusion, 30, 265 (1990); https://doi.org/10.1088/0029-5515/30/2/006.
- K. TOBITA et al., “SlimCS–Compact Low Aspect Ratio DEMO Reactor with Reduced-Size Central Solenoid,” Nucl. Fusion, 47, 829 (2007); https://doi.org/10.1088/0029-5515/47/8/022.
- R. HIWATARI et al., “Demonstration Tokamak Fusion Power Plant for Early Realization for Net Electric Power Generation,” Nucl. Fusion, 45, 96 (2005); https://doi.org/10.1088/0029-5515/45/2/004.
- Y. SAKAMOTO et al., “DEMO Concept Development and Assessment of Relevant Technologies,” IAEA 25th Fusion Energy Conf., FIR/3-4RB, St. Petersburg, Florida (2014); http://www-naweb.iaea.org/napc/physics/FEC/FEC2014/fec2014-preprints/222_FIP34Rb.pdf (current as of Sep. 16, 2016).
- S. NISHIO et al., “Conceptual Design of Tokamak High Power Reactor (ASSTR2),” J. Plasma Fusion Res., 78, 1218 (2002); https://doi.org/10.1585/jspf.78.1218.
- K. OKANO et al., “Compact Reversed Shear Tokamak Reactor with a Superheated Steam Cycle,” Nucl. Fusion, 40, 635 (2000); https://doi.org/10.1088/0029-5515/40/3Y/326.
- ITER DRG1 Annex, Structural Material Database, Article 5. Radiation Limits on Magnets (2001).
- K. HAMADA et al., “Demonstration of Full Scale JJ1 and 316LN Fabrication for ITER TF Coil Structure,” Fusion Eng. Des., 82, 1481 (2007); https://doi.org/10.1016/j.fusengdes.2007.07.032.
- R. J. La HAYE, “Physics of Locked Modes in ITER: Error Field Limits, Rotation for Obviation, and Measurement of Field Errors,” GA-A22468, General Atomics (1997).
- J. T. SCOVILLE et al., “Locked Modes in DIII-D and a Method for Prevention of the Low Density Mode,” Nucl. Fusion, 31, 875 (1991); https://doi.org/10.1088/0029-5515/31/5/006.
- R. YOSHINO et al., “Operational Scenarios to Avoid Disruptions in JT-60U,” J. Plasma Fusion Res., 70, 1081 (1994).
- M. MATSUKAWA et al., “A Conceptual Design Study for the Error Field Correction Coil Power Supply in JT-60SA,” Plasma Sci. Technol., 15, 257 (2013).
- K. TAKANO et al., “Development of Manufacturing Technology of Radial Plate in Superconducting Coil for Fusion Reactor by Diffusion Bonding by Hot Isostatic Pressing,” J. Welding Int., 30, 159 (2016); https://doi.org/10.1080/09507116.2014.921089.
- N. ASAKURA et al., “Investigations of Impurity Seeding and Radiation Control for Long-Pulse and High-Density H-Mode Plasmas in JT-60U,” Nucl. Fusion, 49, 115010 (2009); https://doi.org/10.1088/0029-5515/49/11/115010.
- ITER Organization, “Structural Design Criteria In-Vessel Components (SDC-IC),” IDM 222RHC, ITER (2012).
- V. BARABASH et al., “Codes and Standards and Regulation Issues for Design and Construction of the ITER Mechanical Components,” Fusion Eng. Des., 85, 1290 (2010); https://doi.org/10.1016/j.fusengdes.2010.03.021.
- D. STORK et al., “Developing Structural, High-Heat Flux and Plasma Facing Materials for a Near-Term DEMO Fusion Power Plant: The EU Assessment,” J. Nucl. Mater., 455, 277 (2014); https://doi.org/10.1016/j.jnucmat.2014.06.014.
- G. FEDERICI et al., “Overview of EU DEMO Design and R&D Activities,” Fusion Eng. Des., 89, 882 (2014); https://doi.org/10.1016/j.fusengdes.2014.01.070.
- Y. HOMMA et al., “Numerical Analysis of Tungsten Erosion and Deposition Processes Under a DEMO Divertor Plasma and Geometry,” Nucl. Mater. Energy (to be published).
- M. NAKAJIMA et al., “Corrosion Properties of F82H in Flowing High Temperature Pressurized Water,” J. Plasma Fusion Res. Series, 11, 69 (2015).
- Y. SOMEYA et al., “Design Study of Blanket Structure Based on a Water-Cooled Solid Breeder for DEMO,” Fusion Eng. Des., 98–99, 1872 (2015); https://doi.org/10.1016/j.fusengdes.2015.05.042.
- S. JITSUKAWA et al., “Progress of Reduced Activation Ferritic/Martensitic Steel Development in Japan,” 20th IAEA Fusion Energy Conf., Vilamoura, Portugal FT/1-4 (2004); http://www-pub.iaea.org/MTCD/meetings/PDFplus/fusion-20-preprints/FT_1-4.pdf (current as of Sep. 16, 2016).
- H. TANIGAWA et al., “Development Status of Reduced Activation Ferritic/Martensitic Steels Corresponding to DEMO Design Requirement,” 24th IAEA Fusion Energy Conf., San Diego, California FTP/P7-17 (2012); http://www-naweb.iaea.org/napc/physics/FEC/FEC2012/papers/584_FTPP717.pdf (current as of Sep. 16, 2016).
- K. KATAYAMA et al., “Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition,” Fusion Sci. Technol., 71, 3, 261 (2017); https://doi.org/10.1080/15361055.2017.1288423.
- S. K. SOOD et al., “Fusion Technology Experience at Ontario Hydro’s Darlington Tritium Removal Facility and Heavy Water Upgraders,” Fusion Eng. Des., 12, 356 (1990); https://doi.org/10.1016/0920-3796(90)90009-U.
- K. M. SONG et al., “The Prediction of Tritium Level Reduction of Wolsong NPPs by Heavy Water Detritiation with WTRF,” Fusion Sci. Technol., 48, 290 (2005); https://doi.org/10.13182/FST05-A929.