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Probability of pipe fracture in the primary coolant loop of a PWR plant

Author: Stephen C H Lu; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Lawrence Livermore Laboratory.
Publisher: Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981.
Edition/Format:   eBook : Document : National government publication : EnglishView all editions and formats
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Additional Physical Format: Print version:
Probability of pipe fracture in the primary coolant loop of a PWR plant.
Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981
(OCoLC)7984676
Material Type: Document, Government publication, National government publication, Internet resource
Document Type: Internet Resource, Computer File
All Authors / Contributors: Stephen C H Lu; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Lawrence Livermore Laboratory.
OCLC Number: 645866437
Notes: "NRC FIN No. A-0133."
NUREG/CR-2189, Vol. 1-9.
UCID-18967, Vol. 1-9.
Reproduction Notes: Electronic reproduction. [S.l.] : HathiTrust Digital Library, 2010. MiAaHDL
Description: 1 online resource (9 volumes) : illustrations
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.
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.
Responsibility: prepared for Division of Engineering Technology, Office of Nuclear Research, U.S. Nuclear Regulatory Commission.

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