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

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Bibliographic Details
Imprint:	[Washington, DC] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2011]
Description:	1 online resource (2 v.) : col. ill. ; 28 cm.
Language:	English
Subject:	Light water reactors -- Accidents -- Computer simulation. Nuclear power plants -- Accidents -- Computer simulation. Nuclear fuel rods -- Performance -- Analysis.
Format:	E-Resource U.S. Federal Government Document Book
URL for this record:	http://pi.lib.uchicago.edu/1001/cat/bib/8832559

Hidden Bibliographic Details
Varying Form of Title:	Vol. 2 tittled: FRAPTRAN 1.4:, integral assessment
Other authors / contributors:	Geelhood, K. J. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Pacific Northwest National Laboratory (U.S.)
Notes:	"NUREG/CR-7023." PNNL-19400." Title from title screen (viewed on May 16, 2012). Includes bibliographical references.
Other form:	Print version: FRAPTRAN 1.4
GPO item no.:	1051-H-11 (online)
Govt.docs classification:	Y 3.N 88:25/7023

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