Conceptual design and feasibility analysis of a heat pipe cooled cermet fuel space nuclear reactor for mars surface application
Yuhan Fan, Rui Yan, Shihe Yu, Liang Chen, Yang Zou
Topics & Concepts
CermetMars Exploration ProgramNuclear engineeringConceptual designEnvironmental scienceMaterials scienceAstrobiologyMechanical engineeringPhysicsEngineeringCeramicComposite materialNuclear reactor physics and engineeringNuclear Materials and PropertiesGraphite, nuclear technology, radiation studies