1967Unpublished venueOpen access

BURNUP: A FORTRAN IV CODE FOR COMPUTING U AND Pu FUEL BURNUP FROM U, Pu, AND Nd MASS SPECTROMETRIC MEASUREMENTS.

General Electric Co., Pleasanton, Calif. Nuclear Technology Dept., B. Rider, C. Ruiz, Jr. J. Peterson, T. McLaughlin, F.R. Smith

Open full text 3 citations

Abstract

of such contractor prepares, disseminates, or provides access to, any information

Open-access reader

About this research paper

What this paper is about

of such contractor prepares, disseminates, or provides access to, any information

Why it matters

OpenAlex reports 3 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.

Available abstract

of such contractor prepares, disseminates, or provides access to, any information

Key concepts: Burnup, Fortran, Nuclear engineering, Code (set theory), Computer science, Environmental science, Operating system, Engineering

Related papers

Back to paper searchBrowse research topicsOriginal source
BURNUP: A FORTRAN IV CODE FOR COMPUTING U AND Pu FUEL BURNUP FROM U, Pu, AND Nd MASS SPECTROMETRIC MEASUREMENTS. — Research Paper | ScholarLens