The Resource FRAPCON-3.5, prepared by K.J. Geelhood and W.G. Luscher

FRAPCON-3.5, prepared by K.J. Geelhood and W.G. Luscher

Label
FRAPCON-3.5
Title
FRAPCON-3.5
Statement of responsibility
prepared by K.J. Geelhood and W.G. Luscher
Creator
Contributor
Author
Issuing body
Subject
Language
eng
Cataloging source
GPO
http://library.link/vocab/creatorName
Geelhood, K. J
Government publication
federal national government publication
Illustrations
illustrations
Index
no index present
Literary form
non fiction
Nature of contents
  • dictionaries
  • bibliography
  • technical reports
http://library.link/vocab/relatedWorkOrContributorDate
1979-
http://library.link/vocab/relatedWorkOrContributorName
  • Luscher, W. G.
  • U.S. Nuclear Regulatory Commission
  • Pacific Northwest National Laboratory (U.S.)
http://library.link/vocab/subjectName
  • Nuclear fuel rods
  • Nuclear fuel claddings
  • Nuclear fuel rods
  • Nuclear fuel rods
  • Nuclear power plants
  • Light water reactors
Label
FRAPCON-3.5, prepared by K.J. Geelhood and W.G. Luscher
Instantiates
Publication
Note
  • Title from title screen (viewed on Nov. 27, 2015)
  • "Manuscript completed: May 2014 ; Date published: October 2014."
  • "NUREG/CR-7024, Rev. 1."
  • "PNNL-19418, Rev. 1."
Bibliography note
Includes bibliographical references
Carrier category
online resource
Carrier MARC source
rdacarrier
Color
mixed
Content category
text
Content type MARC source
rdacontent
Contents
v. 1. A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup -- v. 2. Integral assessment
Dimensions
unknown
Extent
1 online resource (2 volumes)
File format
one file format
Form of item
online
Media category
computer
Media MARC source
rdamedia
Other physical details
color illustrations
Specific material designation
remote
System control number
  • (OCoLC)930865214
  • (OCoLC)930865214
Label
FRAPCON-3.5, prepared by K.J. Geelhood and W.G. Luscher
Publication
Note
  • Title from title screen (viewed on Nov. 27, 2015)
  • "Manuscript completed: May 2014 ; Date published: October 2014."
  • "NUREG/CR-7024, Rev. 1."
  • "PNNL-19418, Rev. 1."
Bibliography note
Includes bibliographical references
Carrier category
online resource
Carrier MARC source
rdacarrier
Color
mixed
Content category
text
Content type MARC source
rdacontent
Contents
v. 1. A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup -- v. 2. Integral assessment
Dimensions
unknown
Extent
1 online resource (2 volumes)
File format
one file format
Form of item
online
Media category
computer
Media MARC source
rdamedia
Other physical details
color illustrations
Specific material designation
remote
System control number
  • (OCoLC)930865214
  • (OCoLC)930865214

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