2014•Annals of Nuclear EnergyRequires access

Neutronic analysis and validation of boiling water reactor core designed by MCNPX code

A. Abdelghafar Galahom, I.I. Bashter, Moustafa Aziz

Open publisher page 9 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 9 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: Nuclear engineering, Boiling water reactor, Monte Carlo method, Plutonium, Benchmark (surveying), Nuclear reactor core, Core (optical fiber), Neutron flux

Back to paper search Browse research topics Original source

Neutronic analysis and validation of boiling water reactor core designed by MCNPX code — Research Paper | ScholarLens