Thermal–hydraulics analyses for 1/6 prismatic VHTR core and fuel element with and without bypass flow-Reference-Cited by-同舟云学术

Thermal–hydraulics analyses for 1/6 prismatic VHTR core and fuel element with and without bypass flow

Published:2013-03 Issue: Volume:67 Page:325-341
ISSN:0196-8904
Container-title:Energy Conversion and Management
language:en
Short-container-title:Energy Conversion and Management

Author:

Travis Boyce W.,El-Genk Mohamed S.

Publisher

Elsevier BV

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Reference16 articles.

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3. The gas-turbine modular helium reactor;LaBar;J Nucl Future,2004

4. Schultz RR, Nigg DW, Ougouag AM, Terry WK, Wolf JR, Gougar HD, et al. Next generation nuclear plant-design methods development and validation research and development program plan. INEEL/EXT-04-02293 Rev. 0, Idaho National Engineering and Environmental Laboratory Technical, Report; 2004.

5. Pointer WD, Thomas JW. Steady-state, whole-core prismatic VHTR simulation including core bypass. In: Proceedings ICAPP ’10, American nuclear society, San Diego, CA, 2010: Paper #10310; 2010.

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