The Resource BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test, prepared by K.G. Dewall, R. Steele, Jr

BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test, prepared by K.G. Dewall, R. Steele, Jr

Label
BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test
Title
BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test
Statement of responsibility
prepared by K.G. Dewall, R. Steele, Jr
Creator
Contributor
Subject
Language
eng
http://library.link/vocab/creatorName
DeWall, Kevin G
Government publication
federal national government publication
Illustrations
illustrations
Index
no index present
Literary form
non fiction
Nature of contents
  • bibliography
  • technical reports
http://library.link/vocab/relatedWorkOrContributorName
  • Steele, Robert
  • U.S. Nuclear Regulatory Commission
  • U.S. Nuclear Regulatory Commission
  • Idaho National Engineering Laboratory
http://library.link/vocab/subjectName
  • Boiling water reactors
  • Nuclear power plants
  • Valves
Type of report
Technical.
Label
BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test, prepared by K.G. Dewall, R. Steele, Jr
Instantiates
Publication
Note
  • "Idaho National Engineering Laboratory."
  • Distributed to depository libraries in microfiche
  • Vols. 1-3 no longer available for sale by the Supt. of Docs
  • "Date published: October 1989."
  • "NUREG/CR-5406."
  • "EGG-2569."
Bibliography note
Includes bibliographical references
Carrier category
volume
Carrier category code
nc
Carrier MARC source
rdacarrier
Content category
text
Content type code
txt
Content type MARC source
rdacontent
Contents
v. 1. Analysis and conclusions -- v. 2. Data report -- v. 3. Review of issues associated with BWR containment isolation valve closure
Control code
17226907
Dimensions
28 cm
Extent
volumes
Media category
unmediated
Media MARC source
rdamedia
Media type code
n
Other physical details
illustrations
Stock number
  • 052-021-00197-5 (v. 1)
  • 052-021-00198-3 (v. 2)
  • 052-021-00199-1 (v. 3)
Label
BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test, prepared by K.G. Dewall, R. Steele, Jr
Publication
Note
  • "Idaho National Engineering Laboratory."
  • Distributed to depository libraries in microfiche
  • Vols. 1-3 no longer available for sale by the Supt. of Docs
  • "Date published: October 1989."
  • "NUREG/CR-5406."
  • "EGG-2569."
Bibliography note
Includes bibliographical references
Carrier category
volume
Carrier category code
nc
Carrier MARC source
rdacarrier
Content category
text
Content type code
txt
Content type MARC source
rdacontent
Contents
v. 1. Analysis and conclusions -- v. 2. Data report -- v. 3. Review of issues associated with BWR containment isolation valve closure
Control code
17226907
Dimensions
28 cm
Extent
volumes
Media category
unmediated
Media MARC source
rdamedia
Media type code
n
Other physical details
illustrations
Stock number
  • 052-021-00197-5 (v. 1)
  • 052-021-00198-3 (v. 2)
  • 052-021-00199-1 (v. 3)

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