Reducing the Burden of High Level Radioactive Waste with Transmutation — Proposal of Integral Molten Salt Fast Reactor (IMSFR)

Author:

Yamawaki Michio1,Koyama Tadafumi2

Affiliation:

1. Research Institute of Nuclear Engineering, University of Fukui

2. Central Research Institute of Electrical Power Industries

Publisher

The Japan Society of Nuclear and Radiochemical Sciences

Reference27 articles.

1. (1) K. Nishihara, “Database for Evaluation of Potential Radiotoxicity of Spent Fuel”, JAEA-Data/Code 2010-012, JAEA (2010).

2. (2) “Accelerator-driven systems (ADS) and fast reactors (FR) in advanced nuclear fuel cycles”, URL http://www.oecdnea.org/ndd/reports/2002/nea3109.html, OECD/NEA AEN, (2002).

3. (3) M. Yamawaki et al., 4th chapter, NSA Commentaries No.23, “Technology Development for Decreasing the Amount and Radiotoxicity of High Level Radioactive Waste-Nuclides Separation and Transmutation”, (2016).

4. (4) T. Takeda, 2nd chapter, NSA Commentaries No.23, “Technology Development for Decreasing the Amount and Radiotoxicity of High Level Radioactive Waste-Nuclides Separation and Transmutation”, (2016).

5. (5) T. Mizuno and H. Niwa, “Advanced MOX Core Design Study of Sodium-Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan”, Nucl. Tech., 146, 155 (2004).

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