Coverart for item
The Resource Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2, prepared by G.E. Russcher [and others] ; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2, prepared by G.E. Russcher [and others] ; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Label
Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2
Title
Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor
Title remainder
materials tests 1 and 2
Statement of responsibility
prepared by G.E. Russcher [and others] ; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Creator
Contributor
Author
Subject
Language
eng
Member of
Additional physical form
Also issued online.
Cataloging source
GPO
http://bibfra.me/vocab/lite/collectionName
Technical Report Archive & Image Library (TRAIL)
http://library.link/vocab/creatorName
Russcher, G. E
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
  • Hesson, G. M.
  • King, L. L.
  • Marshall, R. K.
  • Pilger, C. P.
  • Mohr, C. L.
  • Wilson, C. L.
  • Parchen, L. J.
  • U.S. Nuclear Regulatory Commission
  • Pacific Northwest Laboratory
  • United States
  • United States
Series statement
NUREG/CR
Series volume
1735 Add. 1
http://library.link/vocab/subjectName
  • Nuclear reactor accidents
  • Pressurized water reactors
  • Nuclear fuel claddings
  • Nuclear reactor accidents
  • Pressurized water reactors
Label
Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2, prepared by G.E. Russcher [and others] ; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Link
http://www.osti.gov/scitech/servlets/purl/1080210
Instantiates
Publication
Distribution
Note
  • "Pacific Northwest Laboratory."
  • "Date published: September 1981."
  • "NRC FIN B2277."
  • "NUREG/CR-1735, Addendum 1."
  • "PNL-3765."
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
Dimensions
28 cm
Extent
37 pages in various pagings
Media category
unmediated
Media MARC source
rdamedia
Media type code
  • n
Other physical details
illustrations
System control number
  • (OCoLC)08859410
  • (OCoLC)ocm08859410
Label
Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2, prepared by G.E. Russcher [and others] ; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Link
http://www.osti.gov/scitech/servlets/purl/1080210
Publication
Distribution
Note
  • "Pacific Northwest Laboratory."
  • "Date published: September 1981."
  • "NRC FIN B2277."
  • "NUREG/CR-1735, Addendum 1."
  • "PNL-3765."
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
Dimensions
28 cm
Extent
37 pages in various pagings
Media category
unmediated
Media MARC source
rdamedia
Media type code
  • n
Other physical details
illustrations
System control number
  • (OCoLC)08859410
  • (OCoLC)ocm08859410

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