「"U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology"」の検索結果 | NDLサーチ

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Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions [microform] : phase I final report / prepared by S. Majumdar, W. Shack

マイクロ図書

2003<YCA-Y 3.N 88:25/6792>

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著者標目...h) Shack, W. J U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology

Final report on advanced nondestructive evaluation for steam generator tubing for the Second International Steam Generator Tube Integrity Program [microform] / prepared by S. Bakhtiari ... [et al.] NUREG/CR-6814 ANL-03/4

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2003<YCA-Y 3.N 88:25/6814>

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著者標目...nal Laboratory U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology

Knowledge base for the effect of debris on pressurized water reactor emergency core cooling sump performance [electronic resource] / prepared by D.V. Rao, principal investigator ... [et al.] NUREG/CR-6808 LA-UR-03-0880

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2003<YCA-Y 3.N 88:25/6808>

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著者標目...nal Laboratory U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology

Electromagnetic compatibility testing for conducted susceptibility along interconnecting signal lines [microform] : draft report for comment / prepared by P.D. Ewing ... [et al.]

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2002<YCA-Y 3.N 88:25/5609/DRAFT>

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著者標目Ewing, P. D U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology

MOV stem lubricant aging research [microform] / prepared by K.G. DeWall, J.C. Watkins

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2003<YCA-Y 3.N 88:25/6806>

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著者標目...John Clifford) U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology

The effects of composition and heat treatment on hardening and embrittlement of reactor pressure vessel steels [microform] / prepared by G.R. Odette ... [et al.] NUREG/CR-6778

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2003<YCA-Y 3.N 88:25/6778>

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著者標目... Santa Barbara U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology

Results from pressure and leak-rate testing of laboratory-degraded steam generator tubes [microform] / prepared by K. Kasza ... [et al.]

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2002<YCA-Y 3.N 88:25/6789>

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著者標目Kasza, K U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Argonne National Laboratory

Guidance for performing probabilistic seismic hazard analysis for a nuclear plant site [electronic resource] : example application to the southeastern United States / prepared by J.B. Savy ... [et al.]

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2002<YCA-Y 3.N 88:25/6607>

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著者標目Savy, Jean Bernard U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Lawrence Livermore Laboratory

Structural seismic fragility analysis of the Surry containment [microform] / prepared by Eric W. Klamerus

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2002<YCA-Y 3.N 88:25/6783>

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著者標目Klamerus, Eric W U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Sandia National Laboratories

ANL/CANTIA [microform] : a computer code for steam generator integrity assessments / prepared by S. Majumdar

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2002<YCA-Y 3.N 88:25/6786>

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著者標目Majumdar, S. (Saurindranath) U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Argonne National Laboratory

Evaluation current reliability results from the steam generator mock-up analysis round-robin [microform] / prepared by D.S. Kupperman ... [et al.]

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2002<YCA-Y 3.N 88:25/6791>

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著者標目Kupperman, D. S U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Argonne National Laboratory

Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments [microform] / prepared by O.K. Chopra

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2002<YCA-Y 3.N 88:25/6787>

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著者標目Chopra, O. K U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Argonne National Laboratory

Results and analysis of the ASTM round robin on reconstitution [microform] / prepared by K. Onizawa ... [et al.] (HSSI report ; 28)

マイクロ図書

2002<YCA-Y 3.N 88:25/6777>

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著者標目Onizawa, K U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Oak Ridge National Laboratory

Evaluation of eddy current reliability from steam generator mock-up round-robin [microform] / prepared by D.S. Kupperman ... [et al.]

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2002<YCA-Y 3.N 88:25/6785>

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著者標目Kupperman, D. S U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Argonne National Laboratory

GSI-191 [microform] : separate-effects characterization of debris transport in water / prepared by D.V. Rao ... [et al.]

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2002<YCA-Y 3.N 88:25/6772>

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著者標目Rao, D. V U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Los Alamos National Laborator...

Evaluation of aging and qualification practices for cable splices used in nuclear power plants [microform] / prepared by M. Villaran, R. Lofaro

マイクロ図書

2002<YCA-Y 3.N 88:25/6788>

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著者標目Villaran, M Lofaro, R U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Brookhaven National Laborator...

GSI-191 [microform] : the impact of debris induced loss of ECCS recirculation on PWR core damage frequency / prepared by J.L. Darby ... [et al.]

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2002<YCA-Y 3.N 88:25/6771>

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著者標目Darby, John L U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Los Alamos National Laborator...

A comparison of three round robin studies on ISI reliability of wrought stainless steel piping [microform] / prepared by P.G. Heasler, S.R. Doctor

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2003<YCA-Y 3.N 88:25/6795>

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著者標目Heasler, P. G Doctor, S. R U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Pacific Northwest National La...

Validation on failure and leak-rate correlations for stress corrosion cracks in steam generator tubes [microform] / prepared by S. Majumdar ... [et al.]

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2002<YCA-Y 3.N 88:25/6774>

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著者標目Majumdar, S. (Saurindranath) U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Argonne National Laboratory. ...

Advanced nondestructive evaluation for steam generator tubing [microform] / prepared by S. Bakhtiari ... [et al.]

マイクロ図書

2001<YCA-Y 3.N 88:25/6746>

国立国会図書館

著者標目Bakhtiari, Sasan U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology Argonne National Laboratory