Jump to main content

yr 〜
yr

Search results 28

REVIEW AND EVALUATION OF DESIGN ANALYSIS METHODS FOR CALCULATING FLEXIBILITY OF NOZZLES AND BRANCH CONNECTIONS. (NUREG ; NUREG-CR-4785)

REVIEW AND EVALUATION OF DESIGN ANALYSIS METHODS FOR CALCULATING FLEXIBILITY OF NOZZLES AND BRANCH CONNECTIONS. (NUREG ; NUREG-CR-4785)
Paper図書
MOORE, S.E.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

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.

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.

EXPERIMENTAL STRESS ANALYSIS AND FATIGUE TESTS OF FIVE 24-IN. NPS ANSI STANDARD B16.9 TEES. (ORNL ; ORNL-TM-9409)

EXPERIMENTAL STRESS ANALYSIS AND FATIGUE TESTS OF FIVE 24-IN. NPS ANSI STANDARD B16.9 TEES. (ORNL ; ORNL-TM-9409)
Paper図書
MOORE, S.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1985.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

EXPERIMENTAL STRESS ANALYSIS AND FATIGUE TESTS OF FIVE 12-IN. NPS ANSI STANDARD B16.9 TEES. (ORNL ; ORNL-TM-8965)

EXPERIMENTAL STRESS ANALYSIS AND FATIGUE TESTS OF FIVE 12-IN. NPS ANSI STANDARD B16.9 TEES. (ORNL ; ORNL-TM-8965)
Paper図書
MOORE, S.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1984.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

EXPERIMENTAL STRESS ANALYSIS OF FOUR MACHINED 10-IN. NPS PIPING ELBOWS WITH SPECIFIED GEOMETRIC DISTORTIONS. (ORNL ; ORNL-TM-8845)

EXPERIMENTAL STRESS ANALYSIS OF FOUR MACHINED 10-IN. NPS PIPING ELBOWS WITH SPECIFIED GEOMETRIC DISTORTIONS. (ORNL ; ORNL-TM-8845)
Paper図書
MOORE, S.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1983.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

Design Criteria for the Spacing of Nozzles and Reinforced Openings in Cylindrical Nuclear Pressure Vessels and Pipe (NUREG ; NUREG/CR-2308; ORNL-5809)

Design Criteria for the Spacing of Nozzles and Reinforced Openings in Cylindrical Nuclear Pressure Vessels and Pipe (NUREG ; NUREG/CR-2308; ORNL-5809)
Paper図書
Moore, S.E./Mershon, J.L.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.
Other Libraries in Japan
  • Author HeadingMoore, S.E. Mershon, J.L.

GAUGE INVARIANT DESCRIPTION OF HEAVY QUARK BOUND STATES IN QUANTUM CHROMODYNAMICS. (LBL ; LBL-11365)

GAUGE INVARIANT DESCRIPTION OF HEAVY QUARK BOUND STATES IN QUANTUM CHROMODYNAMICS. (LBL ; LBL-11365)
Paper図書
MOORE, S.E.Lawrence Berkeley Laboratory(Lawrence Berkeley Laboratory)1980.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

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.

STRESS INDICES AND FLEXIBILITY FACTORS FOR NOZZLES IN PRESSURE VESSELS AND PIPING (NUREG ; NUREG/CR-0778; ORNL/SUB-2913/10)

STRESS INDICES AND FLEXIBILITY FACTORS FOR NOZZLES IN PRESSURE VESSELS AND PIPING (NUREG ; NUREG/CR-0778; ORNL/SUB-2913/10)
Paper図書
Rodabaugh, E.C./Moore, S.E.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1979.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C. Moore, S.E.

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.

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.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1978.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C. Moore, S.E.

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.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1978.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C. Moore, S.E.

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

DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM. QUARTERLY PROGRESS REPORT, JULY-SEPTEMBER 1976. (ORNL ; ORNL-NUREG-TM-107)

DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM. QUARTERLY PROGRESS REPORT, JULY-SEPTEMBER 1976. (ORNL ; ORNL-NUREG-TM-107)
Paper図書
MOORE, S.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1977.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM QUARTERLY PROGRESS REPORT FOR APRIL-JUNE 1976. (ORNL ; ORNL-NUREG-TM-91)

DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM QUARTERLY PROGRESS REPORT FOR APRIL-JUNE 1976. (ORNL ; ORNL-NUREG-TM-91)
Paper図書
MOORE, S.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1977.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM QUARTERLY PROGRESS REPORT FOR OCTOBER-DECEMBER 1976. (ORNL ; ORNL-NUREG-TM-144)

DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM QUARTERLY PROGRESS REPORT FOR OCTOBER-DECEMBER 1976. (ORNL ; ORNL-NUREG-TM-144)
Paper図書
MOORE, S.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1977.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

PROGRESS REPORT FOR THE DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM FOR THE TWO QUARTERLY PERIODS JULY 1 - SEPTEMBER 30 AND OCTOBER 1 - DECEMBER 31, 1975. (ORNL ; ORNL-NUREG-TM-18)

PROGRESS REPORT FOR THE DESIGN CRITERIA FOR PIPING AND NOZZLES PROGRAM FOR THE TWO QUARTERLY PERIODS JULY 1 - SEPTEMBER 30 AND OCTOBER 1 - DECEMBER 31, 1975. (ORNL ; ORNL-NUREG-TM-18)
Paper図書
MOORE, S.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1976.
Other Libraries in Japan
  • Author HeadingMOORE, S.E.

FLANGED JOINTS WITH CONTACT OUTSIDE THE BOLT CIRCLE; ASME PART B DESIGN RULES (ORNL ; ORNL-Sub-2913)

FLANGED JOINTS WITH CONTACT OUTSIDE THE BOLT CIRCLE; ASME PART B DESIGN RULES (ORNL ; ORNL-Sub-2913)
Paper図書
Rodabaugh, E.C./Moore, S.E.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1976.
Other Libraries in Japan
  • Author HeadingRodabaugh, E.C. Moore, S.E.

Progress Report for the Design Criteria for Piping and Nozzles Program for the Two Quarterly Periods July 1 to Sept. 30 and Oct. 1 to Dec. 31, 1975 (ORNL ; ORNL-NUREG-TM-18)

Progress Report for the Design Criteria for Piping and Nozzles Program for the Two Quarterly Periods July 1 to Sept. 30 and Oct. 1 to Dec. 31, 1975 (ORNL ; ORNL-NUREG-TM-18)
Paper図書
Moore, s.e./Bryson, J.W.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1976.
Other Libraries in Japan
  • Author HeadingMoore, s.e. Bryson, J.W.
RSS