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Functional capability of piping systems microform / D. Terao, E.C. Rodabaugh

Functional capability of piping systems microform / D. Terao, E.C. Rodabaugh
Microform図書
1992<YCA-Y 3.N 88:10/1367>
National Diet Library

Review of ASME code criteria for control of primary loads on nuclear piping system branch connections and recommendations for additional development work [microform] / prepared by E.C. Rodabaugh, R.C. Gwaltney, S.E. Moore

Review of ASME code criteria for control of primary loads on nuclear piping system branch connections and recommendations for additional development work [microform] / prepared by E.C. Rodabaugh, R.C. Gwaltney, S.E. Moore
Microform図書
1993<YCA-Y 3.N 88:25/5358>
National Diet Library

Comments on the leak-before-break concept for nuclear power plant piping systems / E.C. Rodabaugh

Comments on the leak-before-break concept for nuclear power plant piping systems / E.C. Rodabaugh
Microform図書
1985<YCA-Y 3.N 88:25/4305>
National Diet Library

REVIEW OF ELASTIC STRESS AND FATIGUE-TO-FAILURE DATA FOR BRANCH CONNECTIONS AND TEES IN RELATION TO ASME DESIGN CRITERIA FOR NUCLEAR POWER PIPING SYSTEMS. (NUREG ; NUREG/CR-5359)

REVIEW OF ELASTIC STRESS AND FATIGUE-TO-FAILURE DATA FOR BRANCH CONNECTIONS AND TEES IN RELATION TO ASME DESIGN CRITERIA FOR NUCLEAR POWER PIPING SYSTEMS. (NUREG ; NUREG/CR-5359)
Paper図書
RODABAUGH, E.C.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1994.
Other Libraries in Japan
  • Author HeadingRODABAUGH, E.C.

REVIEW OF ASME CODE CRITERIA FOR CONTROL OF PRIMARY LOADS ON NUCLEAR PIPING SYSTEM BRANCH CONNECTIONS AND RECOMMENDATIONS FOR ADDITIONAL DEVELOPMENT WORK (NUREG ; NUREG/CR-5358)

REVIEW OF ASME CODE CRITERIA FOR CONTROL OF PRIMARY LOADS ON NUCLEAR PIPING SYSTEM BRANCH CONNECTIONS AND RECOMMENDATIONS FOR ADDITIONAL DEVELOPMENT WORK (NUREG ; NUREG/CR-5358)
Paper図書
RODABAUGH, E.C.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1993.
Other Libraries in Japan
  • Author HeadingRODABAUGH, E.C.

EVALUATION OF THE CAPACITY OF WELDED ATTACHMENTS TO ELBOWS AS COMPARED TO THE METHODOLOGY OF ASME CODE CASE N-318 (WSRC ; WSRC-MS-91-420)

EVALUATION OF THE CAPACITY OF WELDED ATTACHMENTS TO ELBOWS AS COMPARED TO THE METHODOLOGY OF ASME CODE CASE N-318 (WSRC ; WSRC-MS-91-420)
Paper図書
RAWLS, G.B.// WAIS, E.A.// RODABAUGH, E.C. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1992.
Other Libraries in Japan
  • Author HeadingRAWLS, G.B. WAIS, E.A. RODABAUGH, E.C.

Stress indices and stress intensification factors of pressure vessel and piping components : presented at the joint conference of the Pressure Vessels and Piping, Materials, Nuclear Engineering, Solar Energy Divisions, Denver, Colorado, June 21-25, 1981 / sponsored by the Pressure Vessels and Piping Division, ASME ; edited by R.W. Schneider, E.C. Rodabaugh. (PVP ; v. 50)

Stress indices and stress intensification factors of pressure vessel and piping components : presented at the joint conference of the Pressure Vessels and Piping, Materials, Nuclear Engineering, Solar Energy Divisions, Denver, Colorado, June 21-25, 1981 / sponsored by the Pressure Vessels and Piping Division, ASME ; edited by R.W. Schneider, E.C. Rodabaugh. (PVP ; v. 50)
Paper図書
American Society of Mechanical Engineersc1981.<M15-A5703>
National Diet Library

FRAGILITY TESTS OF WELDED ATTACHMENTS AS COMPARED TO ASME CODE CASE N-318 (WSRC ; WSRC-MS-90-359)

FRAGILITY TESTS OF WELDED ATTACHMENTS AS COMPARED TO ASME CODE CASE N-318 (WSRC ; WSRC-MS-90-359)
Paper図書
RAWLS, G.B.// WAIS, E.A.// RODABAUGH, E.C. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1990.
Other Libraries in Japan
  • Author HeadingRAWLS, G.B. WAIS, E.A. RODABAUGH, E.C.

PREPARATION OF DESIGN SPECIFICATIONS AND DESIGN REPORTS FOR PUMPS, VALVES, PIPING. (NUREG ; NUREG-CR-4943)

PREPARATION OF DESIGN SPECIFICATIONS AND DESIGN REPORTS FOR PUMPS, VALVES, PIPING. (NUREG ; NUREG-CR-4943)
Paper図書
RODABAUGH, E.C.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan
  • Author HeadingRODABAUGH, E.C.

Preparation of design specifications and design reports for pumps, valves, piping, and piping supports used in safety-related portions of nuclear power plants (ORNL/TM ; ORNL/TM-10425)

Preparation of design specifications and design reports for pumps, valves, piping, and piping supports used in safety-related portions of nuclear power plants (ORNL/TM ; ORNL/TM-10425)
Paper図書
Oak Ridge National Lab., TN (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation(Oak Ridge National Lab., TN (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation)1987.
Other Libraries in Japan
  • Author HeadingMoore, S.E. Rodabaugh, E.C.

COMMENTS ON THE LEAK-BEFORE-BREAK CONCEPT FOR NUCLEAR POWER PLANT PIPING SYSTEMS (NUREG ; NUREG/CR-4305; ORNL/SUB/82-22252/3)

COMMENTS ON THE LEAK-BEFORE-BREAK CONCEPT FOR NUCLEAR POWER PLANT PIPING SYSTEMS (NUREG ; NUREG/CR-4305; ORNL/SUB/82-22252/3)
Paper図書
Rodabaugh, E.C.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C.

Review and evaluation of design analysis methods for calculating flexibility of nozzles and branch connections (ORNL ; ORNL-6339)

Review and evaluation of design analysis methods for calculating flexibility of nozzles and branch connections (ORNL ; ORNL-6339)
Paper図書
Oak Ridge National Laboratory(Oak Ridge National Laboratory)1987.
Other Libraries in Japan
  • Author HeadingGwaltney, R.C. Mokhtarian, K. Moore, S.E. Rodabaugh, E.C.

Comparisons of ASME-code fatigue-evaluation methods for nuclear Class 1 piping with Class 2 or 3 piping (ORNL/SUB ; ORNL/SUB--82-22252/1)

Comparisons of ASME-code fatigue-evaluation methods for nuclear Class 1 piping with Class 2 or 3 piping (ORNL/SUB ; ORNL/SUB--82-22252/1)
Paper図書
Rodabaugh (E.C.) and Associates, Hilliard, OH (USA)(Rodabaugh (E.C.) and Associates, Hilliard, OH (USA))1983.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C.

SOURCES OF UNCERTAINTY IN THE CALCULATION OF LOADS ON SUPPORTS OF PIPING SYSTEMS. (NUREG ; NUREG-CR-3599)

SOURCES OF UNCERTAINTY IN THE CALCULATION OF LOADS ON SUPPORTS OF PIPING SYSTEMS. (NUREG ; NUREG-CR-3599)
Paper図書
RODABAUGH, E.C.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1984.
Other Libraries in Japan
  • Author HeadingRODABAUGH, E.C.

COMPARISONS OF ASME CODE FATIGUE EVALUATION METHODS FOR NUCLEAR CLASS 1 PIPING WITH CLASS 2 OR 3 PIPING. (NUREG ; NUREG-CR-3243)

COMPARISONS OF ASME CODE FATIGUE EVALUATION METHODS FOR NUCLEAR CLASS 1 PIPING WITH CLASS 2 OR 3 PIPING. (NUREG ; NUREG-CR-3243)
Paper図書
RODABAUGH, E.C.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1983.
Other Libraries in Japan
  • Author HeadingRODABAUGH, E.C.

Realistic Seismic Design Margins of Pumps, Valves, and Piping (NUREG ; NUREG/CR-2137; ORNL/SUB-2913/11)

Realistic Seismic Design Margins of Pumps, Valves, and Piping (NUREG ; NUREG/CR-2137; ORNL/SUB-2913/11)
Paper図書
Rodabaugh, E.C./Desai, K.D.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1981.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C. Desai, K.D.

Stress indices and stress intensification factors of prssure vessel and piping components: Presented at the joint conference of the pressure vessels and piping, materials, nuclear engineering, solar energy divisions. (PVP-V.50)

Stress indices and stress intensification factors of prssure vessel and piping components: Presented at the joint conference of the pressure vessels and piping, materials, nuclear engineering, solar energy divisions. (PVP-V.50)
Paper図書
Schneider, R.W.(ed.)/Rodabaugh, E.C.(ed.)ASME1981.
Other Libraries in Japan
  • Author HeadingSchneider, R.W. Rodabaugh, E.C.

Stress indices for girth welded joints, including radial weld shrinkage, mismatch and tapered-wall transitions (NUREG ; NUREG/CR-0371; ORNL/Sub-2913/9)

Stress indices for girth welded joints, including radial weld shrinkage, mismatch and tapered-wall transitions (NUREG ; NUREG/CR-0371; ORNL/Sub-2913/9)
Paper図書
Rodabaugh, E.C., Moore, S.E.Battelle Columbus Labs.1978.9.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C. Moore, S.E.

END EFFECTS ON ELBOWS SUBJECTED TO MOMENT LOADINGS. (ORNL ; ORNL-SUB-2913-7)

END EFFECTS ON ELBOWS SUBJECTED TO MOMENT LOADINGS. (ORNL ; ORNL-SUB-2913-7)
Paper図書
RODABAUGH, E.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1978.
Other Libraries in Japan
  • Author HeadingRODABAUGH, E.C.

Evaluation of the plastic characteristics of piping products in relation to ASME code criteria (NUREG ; NUREG/CR-0261; ORNL/Sub-2913/8)

Evaluation of the plastic characteristics of piping products in relation to ASME code criteria (NUREG ; NUREG/CR-0261; ORNL/Sub-2913/8)
Paper図書
Rodabaugh, E.C., Moore, S.E.Oak Ridge National Lab.1978.7.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C. Moore, S.E.
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