FRAPTRAN-1.5 / prepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta.

Format:

Book

Government document

Author/Creator:

Geelhood, K. J., author.

Luscher, W. G. (Walter G.), 1979- author.

Cuta, J. M., author.

Contributor:

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, issuing body.

Pacific Northwest National Laboratory (U.S.)

Language:

English

Subjects (All):

Nuclear fuel rods--Computer simulation.

Nuclear fuel rods.

Nuclear fuel rods--Performance--Analysis.

Nuclear fuel rods--Data processing.

Nuclear fuel claddings--Data processing.

Nuclear fuel claddings.

Nuclear power plants--Computer simulation.

Nuclear power plants.

Physical Description:

1 online resource (2 volumes) : color illustrations

Place of Publication:

Washington, D.C. : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, October 2014.

Contents:

Vol. 1. A computer code for the transient analysis of oxide fuel rods

vol. 2. Integral assessment.

Notes:

Title from title screen (viewed on Nov. 30, 2015).

"NUREG/CR-7023, Rev. 1."

"PNNL-19400."

Includes bibliographical references.

"Manuscript completed: May 2014 ; Date published: October 2014."

Other Format:

Print version: Geelhood, K.J. FRAPTRAN-1.5

OCLC:

930784880