The Resource Probability of pipe fracture in the primary coolant loop of a PWR plant, prepared for Division of Engineering Technology, Office of Nuclear Research, U.S. Nuclear Regulatory Commission

Probability of pipe fracture in the primary coolant loop of a PWR plant, prepared for Division of Engineering Technology, Office of Nuclear Research, U.S. Nuclear Regulatory Commission

Label
Probability of pipe fracture in the primary coolant loop of a PWR plant
Title
Probability of pipe fracture in the primary coolant loop of a PWR plant
Statement of responsibility
prepared for Division of Engineering Technology, Office of Nuclear Research, U.S. Nuclear Regulatory Commission
Creator
Contributor
Author
Subject
Language
eng
Member of
Action
digitized
Cataloging source
OCLCE
http://bibfra.me/vocab/lite/collectionName
Technical Report Archive & Image Library (TRAIL)
http://library.link/vocab/creatorName
Lu, Stephen C. H
Government publication
federal national government publication
Illustrations
illustrations
Index
no index present
LC call number
TK9202
LC item number
.P7 1981
Literary form
non fiction
Nature of contents
  • dictionaries
  • bibliography
http://library.link/vocab/relatedWorkOrContributorName
  • Streit, R. D.
  • Chou, C. K.
  • Eberhardt, A. C.
  • Chan, A. L.
  • Lu, S. C.
  • Rybicki, E. F.
  • Curtis, D. J.
  • Ma, S. M.
  • Larder, R. A.
  • Harris, D. O.
  • Lim, E. Y.
  • Dedhia, D. D.
  • Mensing, R.
  • George, L.
  • Lawrence Livermore Laboratory
Series statement
NUREG/CR
Series volume
2189/v. 1-9
http://library.link/vocab/subjectName
  • Structural design
  • Structural dynamics
  • Nuclear power plants
  • Nuclear power plants
  • United States
Label
Probability of pipe fracture in the primary coolant loop of a PWR plant, prepared for Division of Engineering Technology, Office of Nuclear Research, U.S. Nuclear Regulatory Commission
Link
Instantiates
Publication
Distribution
Note
  • "Load combination program project I final report."
  • "Lawrence Livermore Laboratory."
  • "Date published: August 1981" (v. 3,5,9)
  • "Date published: September 1981" (v. 1,2,4,6,7,8)
  • "NRC FIN No. A-0133."
  • NUREG/CR-2189, Vol. 1-9
  • UCID-18967, Vol. 1-9
Antecedent source
file reproduced from original
Bibliography note
Includes bibliographical references
Carrier category
online resource
Carrier category code
  • cr
Carrier MARC source
rdacarrier
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Contents
v. 1. Summary / S. Lu, R.D. Streit, C.K. Chou -- v. 2. Primary coolant loop model / A.C. Eberhardt -- v. 3. Nonseismic stress analysis / A.L. Chan [and others] -- v. 4. Seismic response analysis / S.C. Lu, M. Ma, R.A. Larder -- v. 5. Probabilistic fracture mechanics analysis / D.O. Harris, E.Y. Lim, D.D. Dedhia -- v. 6. Failure mode analysis / R.D. Streit -- v. 7. System failure probability analysis / R. Mensing, L. George -- v. 8. Pipe fracture indirectly induced by an earthquake / R.D. Streit -- v. 9. PRAISE computer code user's manual / E.Y. Lim
Dimensions
unknown
Extent
1 online resource (9 volumes)
File format
one file format
Form of item
online
Media category
computer
Media MARC source
rdamedia
Media type code
  • c
Other physical details
illustrations
Reproduction note
Electronic reproduction.
Specific material designation
remote
System control number
  • (OCoLC)1103315205
  • (OCoLC)on1103315205
System details
Master and use copy. Digital master created according to Benchmark for Faithful Digital Reproductions of Monographs and Serials, Version 1. Digital Library Federation, December 2002.
Label
Probability of pipe fracture in the primary coolant loop of a PWR plant, prepared for Division of Engineering Technology, Office of Nuclear Research, U.S. Nuclear Regulatory Commission
Link
Publication
Distribution
Note
  • "Load combination program project I final report."
  • "Lawrence Livermore Laboratory."
  • "Date published: August 1981" (v. 3,5,9)
  • "Date published: September 1981" (v. 1,2,4,6,7,8)
  • "NRC FIN No. A-0133."
  • NUREG/CR-2189, Vol. 1-9
  • UCID-18967, Vol. 1-9
Antecedent source
file reproduced from original
Bibliography note
Includes bibliographical references
Carrier category
online resource
Carrier category code
  • cr
Carrier MARC source
rdacarrier
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Contents
v. 1. Summary / S. Lu, R.D. Streit, C.K. Chou -- v. 2. Primary coolant loop model / A.C. Eberhardt -- v. 3. Nonseismic stress analysis / A.L. Chan [and others] -- v. 4. Seismic response analysis / S.C. Lu, M. Ma, R.A. Larder -- v. 5. Probabilistic fracture mechanics analysis / D.O. Harris, E.Y. Lim, D.D. Dedhia -- v. 6. Failure mode analysis / R.D. Streit -- v. 7. System failure probability analysis / R. Mensing, L. George -- v. 8. Pipe fracture indirectly induced by an earthquake / R.D. Streit -- v. 9. PRAISE computer code user's manual / E.Y. Lim
Dimensions
unknown
Extent
1 online resource (9 volumes)
File format
one file format
Form of item
online
Media category
computer
Media MARC source
rdamedia
Media type code
  • c
Other physical details
illustrations
Reproduction note
Electronic reproduction.
Specific material designation
remote
System control number
  • (OCoLC)1103315205
  • (OCoLC)on1103315205
System details
Master and use copy. Digital master created according to Benchmark for Faithful Digital Reproductions of Monographs and Serials, Version 1. Digital Library Federation, December 2002.

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