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PWR Corrosion Control in the Nuclear Industry
As many Pressurized Water Reactors (PWRs) approach or exceed 40 years of operation, maintaining asset integrity under aging infrastructure, tight outage schedules, and strict ALARA (As Low As Reasonably Achievable) mandates is a real challenge.
T. Sugie, T. Hatae, Y. Koide, T. Fujita, Y. Kusama, T. Nishitani, A. Isayama, M. Sato, K. Shinohara, N. Asakura, S. Konoshima, H. Kubo, H. Takenaga, Y. Kawano, T. Kondoh, A. Nagashima, T. Fukuda, H. Sunaoshi, O. Naito, S. Kitamura, Y. Tsukahara, A. Sakasai, Y. Sakamoto, T. Suzuki, K. Tobita, M. Nemoto, A. Morioka, M. Ishikawa, S. Ishida, N. Isei, N. Oyama, Y. Neyatani, K. Itami, S. Sakurai, H. Tamai, K. Tsuchiya, S. Higashijima, T. Nakano, S. Nagaya, S. Chiba, S. Lee, M. Shitomi
Fusion Science and Technology | Volume 42 | Number 2 | September-November 2002 | Pages 482-511
Technical Paper | doi.org/10.13182/FST02-A242
Articles are hosted by Taylor and Francis Online.
The diagnostic system of JT-60U (JT-60upgrade) is composed of about 50 individual diagnostic devices. Recently, the detailed radial profile measurements of plasma parameters have been improved, so that the internal structure of plasmas could be explored. The understanding of plasma confinement has been enhanced by density and temperature fluctuation measurements using a mm-wave reflectometer and electron cyclotron emission measurements, respectively. In addition, real-time control experiments of electron density, neutron yield, radiated power, and electron temperature gradient have been carried out successfully by corresponding diagnostic devices. These measurements and the real-time control contribute to improving plasma performance. Diagnostic devices for next generation fusion devices such as a CO2 laser interferometer/polarimeter and a CO2 laser collective Thomson scattering system have been developed.