Neutronics and Thermal Hydraulics Analysis of a Conceptual Ultra-High Temperature MHD Cermet Fuel Core for Nuclear Electric Propulsion-Reference-Cited by-同舟云学术

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Neutronics and Thermal Hydraulics Analysis of a Conceptual Ultra-High Temperature MHD Cermet Fuel Core for Nuclear Electric Propulsion

Published:2018-04-16 Issue: Volume:6 Page:
ISSN:2296-598X
Container-title:Frontiers in Energy Research
language:
Short-container-title:Front. Energy Res.

Author:

Song Jian,An Weijian,Wu Yingwei,Tian Wenxi

Funder

National Natural Science Foundation of China

Publisher

Frontiers Media SA

Subject

Economics and Econometrics,Energy Engineering and Power Technology,Fuel Technology,Renewable Energy, Sustainability and the Environment

Reference17 articles.

1. Small fast spectrum reactor designs suitable for direct nuclear thermal propulsion;Bruce,2012

2. Literature review of thermal and radiation performance parameters for high-temperature, uranium dioxide fueled cermet materials;Haertling;J. Nucl. Mater.,2007

3. Ultrahigh temperature vapor-core reactor magnetohydrodynamic system for space nuclear electric power;Isaac;J. Propuls. Power,1993

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