Journal Article

·2004

Rejuvenation of spent fuel in the force-free helical reactor (FFHR)

Hüseyin Yapıcı , Murat Gökçek YTU

Annals of Nuclear Energy

No open-access abstract is available for this article. Use the DOI link on the right to read the full text.

Keywords

Nuclear engineering MOX fuel Spent nuclear fuel Blanket Neutron transport Materials science Fusion power Spent fuel pool Environmental science Nuclear physics Neutron Physics Plutonium Engineering Composite material Plasma

Subject Areas

Magnetic confinement fusion research ·Nuclear and High Energy Physics ·Physical Sciences
Fusion materials and technologies ·Materials Chemistry ·Physical Sciences
Nuclear reactor physics and engineering ·Aerospace Engineering ·Physical Sciences

OpenAlex SDG Match

SDGs auto-classified by OpenAlex (score ≥ 0.4 shown).

Affordable and clean energy 73%

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