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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
  • Author HeadingTerao, D Rodabaugh, E. C U.S. Nuclear Regulatory Commi...

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
  • Author HeadingRodabaugh, E. C Gwaltney, R. C Moore, S. E. (...

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
  • Author HeadingRodabaugh, E. C U.S. Nuclear Regulatory Commi...

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

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

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

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
  • Author Heading...hneider, R. W. Rodabaugh, E. C. American Society of Mechanic...

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

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

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

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

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

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

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

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

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

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

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

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

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
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