ScholarLens Back to search
2010•Annals of Nuclear EnergyRequires access

Determination of fissile fraction in MOX (mixed U+Pu oxides) fuels for different burnup values

L. Ozdemir, Banu Bulut Acar, Okan H. Zabunoğlu

Open publisher page 11 citations

Abstract

This record does not include an abstract. Use the full-text link above if available.

About this research paper

What this paper is about

An abstract is not available in the OpenAlex record for this paper.

Why it matters

OpenAlex reports 11 citations for this work. Citation counts describe recorded attention and do not establish research quality.

Key contribution

A contribution statement is not available in the OpenAlex record.

Method / approach

Method details are not available in the OpenAlex metadata.

Main findings

Findings are not separately available in the OpenAlex metadata.

Limitations

Limitations are not available in the OpenAlex metadata.

Applications

Application details are not available in the OpenAlex metadata.

Key concepts: MOX fuel, Burnup, Fissile material, Plutonium, Nuclear engineering, Spent nuclear fuel, Natural uranium, Radiochemistry

Related papers

Related paper 1Related paper 2Related paper 3
Back to paper searchBrowse research topicsOriginal source
Determination of fissile fraction in MOX (mixed U+Pu oxides) fuels for different burnup values — Research Paper | ScholarLens