FRAPTRAN 1.4 : a computer code for the transient analysis of oxide fuel rods /

Bibliographic Details
Corporate Authors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Pacific Northwest National Laboratory (U.S.)
Other Authors:	Geelhood, K. J.
Format:	Government Document eBook
Language:	English
Published:	[Washington, DC] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2011]
Subjects:	Light water reactors > Accidents > Computer simulation. Nuclear power plants > Accidents > Computer simulation. Nuclear fuel rods > Performance > Analysis.
Online Access:	https://purl.fdlp.gov/GPO/gpo22780

Available Online