The Resource Reliability study, (microform)

Reliability study, (microform)

Label
Reliability study
Title
Reliability study
Contributor
Subject
Genre
Language
eng
Cataloging source
GPO
Government publication
federal national government publication
Illustrations
illustrations
Index
no index present
Literary form
non fiction
Nature of contents
  • bibliography
  • technical reports
Period covered
  • 01/01/87-12/31/95 (v. 1).
  • 1984-1985 (v. 2).
  • 01/01/1984-12/31/1995 (v. 3).
  • 01/01/87-12/31/93 (v. 4-8).
  • 01/01/1987-12/31/1987 (v. 9).
  • 01/01/1984-12/31/1998 (v. 10-11).
http://library.link/vocab/relatedWorkOrContributorName
  • U.S. Nuclear Regulatory Commission
  • U.S. Nuclear Regulatory Commission
  • Idaho National Engineering and Environmental Laboratory
http://library.link/vocab/subjectName
  • Nuclear power plants
  • Pressurized water reactors
  • Boiling water reactors
  • Diesel motor
Type of report
  • Technical.
  • Technical.
  • Technical.
  • Technical.
  • Technical.
  • Technical.
Label
Reliability study, (microform)
Instantiates
Publication
Note
  • "Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Vols. 4-11
  • "Idaho National Engineering and Environmental Laboratory, Lockheed Martin Idaho Technologies Company."
  • Shipping list no.: 98-1081-M (v. 1), 99-0533-M (v. 2), 99-0756-M (v. 3), 2000-0095-M (v. 4, 6, 8), 2000-0142-M (v. 5), 2000-0119-M (v. 7), 2001-0100-M (v. 9), 2002-0537-M (v. 10-11)
  • "Date published: August 1998" (v. 1); "Date published: April 1999" (v. 2); "Date published: May 1999" (v. 3); "Date published: September 1999" (v. 4-8); "Date published: October 2000" (v. 9); "Date published: July 2002" (v. 10); "Date published: July 2002" (v. 11)
  • Paper version no longer available for sale by the Supt. of Docs
  • "NUREG/CR-5500" (v.1- ); "INEL-94/0158" (v. 4); "INEL-95/0035" (v. 5); "INEL-95/0478" (v. 6); "INEL-95/0196" (v. 7); "INEL-95/00133" (v. 8); "INEL/EXT-99-00373" (v. 9); "INEL/EXT-97-00740" (v. 10-11)
Base of film
safety base undetermined
Bibliography note
Includes bibliographical references
Carrier category
microfiche
Carrier category code
  • he
Carrier MARC source
rdacarrier
Color
black and white
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Contents
v. 1. Auxiliary/emergency feedwater system, 1987-1995 / prepared by J.P. Poloski ... [et al.] -- v. 2. Westinghouse reactor protection system, 1984-1995 / prepared by S.A. Eide ... [et al.] -- v. 3. General Electric Reactor Protection System, 1984-1995 / prepared by S.A. Eide ... [et al.] -- v. 4. High-pressure coolant injection (HPCI) system, 1987-1993 / prepared by G.M. Grant ... [et al.] -- v. 5. Emergency diesel generator power system, 1987-1993 -- v. 6. Isolation condenser system, 1987-1993 / prepared by G.M. Grant ... [et al.] -- v. 7. Reactor core isolation cooling system, 1987-1993 / prepared by J.P. Poloski ... [et al.] -- v. 8. High-pressure core spray system, 1987-1993 / prepared by J.P. Poloski ... [et al.] -- v. 9. High-pressure safety injection system, 1987-1997 . prepared by J.P. Poloski ... [et al.] -- v. 10. Combustion engineering reactor protection system, 1984-1998 / prepared by T.E. Wierman -- v. 11. Babcock & Wilcox reactor protection system, 1984-1998 / prepared by T.E. Wierman ... [et al.]
Control code
40638966
Dimensions
28 cm
Dimensions
4x6 in. or 11x15 cm.
Emulsion on film
diazo
Extent
volumes
Form of item
microfiche
Generation
service copy
Media category
microform
Media MARC source
rdamedia
Media type code
  • h
Other physical details
illustrations
Positive negative aspect
negative
http://bibfra.me/vocab/marc/reductionRatio
02
ReductionRatioRange
normal reduction
Reproduction note
Microfiche.
Specific material designation
microfiche
System control number
  • tmp97131592
  • (GPO)99121292
Label
Reliability study, (microform)
Publication
Note
  • "Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Vols. 4-11
  • "Idaho National Engineering and Environmental Laboratory, Lockheed Martin Idaho Technologies Company."
  • Shipping list no.: 98-1081-M (v. 1), 99-0533-M (v. 2), 99-0756-M (v. 3), 2000-0095-M (v. 4, 6, 8), 2000-0142-M (v. 5), 2000-0119-M (v. 7), 2001-0100-M (v. 9), 2002-0537-M (v. 10-11)
  • "Date published: August 1998" (v. 1); "Date published: April 1999" (v. 2); "Date published: May 1999" (v. 3); "Date published: September 1999" (v. 4-8); "Date published: October 2000" (v. 9); "Date published: July 2002" (v. 10); "Date published: July 2002" (v. 11)
  • Paper version no longer available for sale by the Supt. of Docs
  • "NUREG/CR-5500" (v.1- ); "INEL-94/0158" (v. 4); "INEL-95/0035" (v. 5); "INEL-95/0478" (v. 6); "INEL-95/0196" (v. 7); "INEL-95/00133" (v. 8); "INEL/EXT-99-00373" (v. 9); "INEL/EXT-97-00740" (v. 10-11)
Base of film
safety base undetermined
Bibliography note
Includes bibliographical references
Carrier category
microfiche
Carrier category code
  • he
Carrier MARC source
rdacarrier
Color
black and white
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Contents
v. 1. Auxiliary/emergency feedwater system, 1987-1995 / prepared by J.P. Poloski ... [et al.] -- v. 2. Westinghouse reactor protection system, 1984-1995 / prepared by S.A. Eide ... [et al.] -- v. 3. General Electric Reactor Protection System, 1984-1995 / prepared by S.A. Eide ... [et al.] -- v. 4. High-pressure coolant injection (HPCI) system, 1987-1993 / prepared by G.M. Grant ... [et al.] -- v. 5. Emergency diesel generator power system, 1987-1993 -- v. 6. Isolation condenser system, 1987-1993 / prepared by G.M. Grant ... [et al.] -- v. 7. Reactor core isolation cooling system, 1987-1993 / prepared by J.P. Poloski ... [et al.] -- v. 8. High-pressure core spray system, 1987-1993 / prepared by J.P. Poloski ... [et al.] -- v. 9. High-pressure safety injection system, 1987-1997 . prepared by J.P. Poloski ... [et al.] -- v. 10. Combustion engineering reactor protection system, 1984-1998 / prepared by T.E. Wierman -- v. 11. Babcock & Wilcox reactor protection system, 1984-1998 / prepared by T.E. Wierman ... [et al.]
Control code
40638966
Dimensions
28 cm
Dimensions
4x6 in. or 11x15 cm.
Emulsion on film
diazo
Extent
volumes
Form of item
microfiche
Generation
service copy
Media category
microform
Media MARC source
rdamedia
Media type code
  • h
Other physical details
illustrations
Positive negative aspect
negative
http://bibfra.me/vocab/marc/reductionRatio
02
ReductionRatioRange
normal reduction
Reproduction note
Microfiche.
Specific material designation
microfiche
System control number
  • tmp97131592
  • (GPO)99121292

Library Locations

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      1 University Blvd, St. Louis, MO, 63121, US
      38.710138 -90.311107
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