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2. The Future of Nuclear Power: an interdisciplinary MIT study, 2003.

3. The Future of Nuclear Fuel Cycle: an interdisciplinary MIT study, 2010.

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1. Caldarola L. A theoretical model for the molten fuel-sodium interaction in a nuclear fast reactor // Nuclear Engineering and Design 22. 1972. . 175—211.

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1.Smith B.L. Assessment of CFD Codes Used in Nuclear Reactor Safety Simulations // Nuclear Engineering and Technology. 2010. V.42. No.4.

2.Ansys Fluent 12.0. Theory Guide. Ansys, Inc. 2009.

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