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Your search keyword '"Muroga, T."' showing total 2 results
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2 results on '"Muroga, T."'

1. Overview of the TITAN project

Author

Muroga, T., Sze, D.K., and Okuno, K.

Subjects
*TRITIUM, *IRRADIATION, *FLUID dynamics, *NUCLEAR fusion, *NUCLEAR engineering
Abstract

Abstract: This is an overview paper of the joint TITAN (Tritium, Irradiation, and Thermofluid for America and Nippon) project of the Japan–USA fusion cooperation program. The objectives, tasks structure, and technical highlights of the TITAN project are presented, as well as the direction of the project toward its end in March 2013. [Copyright &y& Elsevier]

Published
2012
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2. Recent progress of R&D activities on reduced activation ferritic/martensitic steels.

Author

Huang, Q., Baluc, N., Dai, Y., Jitsukawa, S., Kimura, A., Konys, J., Kurtz, R.J., Lindau, R., Muroga, T., Odette, G.R., Raj, B., Stoller, R.E., Tan, L., Tanigawa, H., Tavassoli, A.-A.F., Yamamoto, T., Wan, F., and Wu, Y.

Subjects
*RESEARCH & development projects, *FERRITIC steel, *NUCLEAR fusion, *NUCLEAR reactors
Abstract

Abstract: Several types of reduced activation ferritic/martensitic (RAFM) steel have been developed over the past 30years in China, Europe, India, Japan, Russia and the USA for application in ITER test blanket modules (TBMs) and future fusion DEMO and power reactors. The progress has been particularly important during the past few years with evaluation of mechanical properties of these steels before and after irradiation and in contact with different cooling media. This paper presents recent RAFM steel results obtained in ITER partner countries in relation to different TBM and DEMO options. [Copyright &y& Elsevier]

Published
2013
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