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Search results 31

Development of J-integral based UT flaw acceptance criteria for Savannah River reactor tanks (WSRC ; WSRC-MS-91-179)

Development of J-integral based UT flaw acceptance criteria for Savannah River reactor tanks (WSRC ; WSRC-MS-91-179)
Paper図書
Mehta, H.S. [et al.]Westinghouse Savannah River Co.1991.
Other Libraries in Japan
  • Author HeadingMehta, H.S. Ranganath, S. Awadalla, N.G. ...

DOUBLE-ENDED BREAK PROBABILITY ESTIMATE FOR THE 304 STAINLESS STEEL MAIN CIRCULATION PIPING OF A PRODUCTION REACTOR (WSRC ; WSRC-MS-91-170)

DOUBLE-ENDED BREAK PROBABILITY ESTIMATE FOR THE 304 STAINLESS STEEL MAIN CIRCULATION PIPING OF A PRODUCTION REACTOR (WSRC ; WSRC-MS-91-170)
Paper図書
MEHTA,H.S.//DAUGHERTY, W.L.//AWADALLA,N.G.//SINDELAR,R.L.(WESTINGHOUSE SAVANNAH RIVER CO.,AIKEN,SC(UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1991.
Other Libraries in Japan

Fracture mechanics : applications and new materials : technology in a global society : presented at the 1993 Pressure Vessels and Piping Conference, Denver, Colorado, July 25-29, 1993

Fracture mechanics : applications and new materials : technology in a global society : presented at the 1993 Pressure Vessels and Piping Conference, Denver, Colorado, July 25-29, 1993
Paper図書
sponsored by the Pressure Vessels and Piping Division, ASME ; edited by H.S. MehtaAmerican Society of Mechanical Engineersc1993
Other Libraries in Japan

FAILURE PROBABILITY ESTIMATE OF TYPE 304 STAINLESS STEEL PIPING (WSRC ; WSRC-MS-90-38)

FAILURE PROBABILITY ESTIMATE OF TYPE 304 STAINLESS STEEL PIPING (WSRC ; WSRC-MS-90-38)
Paper図書
DAUGHERTY, W.L.// AWADALLA, N.G.// SINDELAR, R.L.// MEHTA, H.S.(WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC(USA))Washington Savannah River Company(Washington Savannah River Company)1990.
Other Libraries in Japan
  • Author HeadingDAUGHERTY, W.L. AWADALLA, N.G. SINDELAR, R.L. MEHTA, H.S.

Application of the Leak-Before-Break Approach to BWR Piping (EPRI ; EPRI-NP-4991)

Application of the Leak-Before-Break Approach to BWR Piping (EPRI ; EPRI-NP-4991)
Paper図書
Mehta, H.S./Patel, N.T.Electric Power Research Institute(Electric Power Research Institute)1986.
Other Libraries in Japan
  • Author HeadingMehta, H.S. Patel, N.T.

Stress corrosion cracking literature review and analysis for the Savannah River Plant (NEDC ; NEDC-30837)

Stress corrosion cracking literature review and analysis for the Savannah River Plant (NEDC ; NEDC-30837)
Paper図書
Gordon, B.M., Mehta, H.S.General Electric Co.1984.12.
Other Libraries in Japan
  • Author HeadingGordon, B.M. Mehta, H.S.

"Evaluation of Indications Detected in Annulus Core Spray Piping at Pilgrim Nuclear Station."

"Evaluation of Indications Detected in Annulus Core Spray Piping at Pilgrim Nuclear Station."
Paper図書
BOTHNE, D.//MEHTA, H. S.GENERAL ELECTRIC CO.1997/03/18.
Other Libraries in Japan

GE-NE-B13-02010-33NP, "Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation."

GE-NE-B13-02010-33NP, "Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation."
Paper図書
CAINE, T. A.//MEHTA, H. S.//STARK, R. R.GENERAL ELECTRIC CO.1999/06/30.
Other Libraries in Japan

Rev 0 to GE-NE-B13-01980-030-2, "Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1."

Rev 0 to GE-NE-B13-01980-030-2, "Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1."
Paper図書
CAINE, T. A.//HORN, R. M.//MEHTA, H. S.GENERAL ELECTRIC CO.1998/11/30.
Other Libraries in Japan

Rev 0 to GE-NE-B13-01980-30-1, "Fracture Mechanics Evaluation on Observed Indications at Two Welds In Recirculation Piping of Quad Cities,Unit 1 Station."

Rev 0 to GE-NE-B13-01980-30-1, "Fracture Mechanics Evaluation on Observed Indications at Two Welds In Recirculation Piping of Quad Cities,Unit 1 Station."
Paper図書
CAINE, T. A.//MEHTA, H. S.//STARK, R. R.GENERAL ELECTRIC CO.1998/11/30.
Other Libraries in Japan

Rev 0 to GE-NE-B13-01980-24, "Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station."

Rev 0 to GE-NE-B13-01980-24, "Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station."
Paper図書
LAI, W. C.//MEHTA, H. S.//STARK, R. R.GENERAL ELECTRIC CO.1998/10/31.
Other Libraries in Japan

Non-proprietary rev 0 to GENE-187-30-1598 NP, "CRD Bolting Flaw Evaluation for JA FitzPatrick Nuclear Power Plant."

Non-proprietary rev 0 to GENE-187-30-1598 NP, "CRD Bolting Flaw Evaluation for JA FitzPatrick Nuclear Power Plant."
Paper図書
CAINE, T. A.//MEHTA, H. S.//VAN, DIEMEN. S.GENERAL ELECTRIC CO.1998/10/30.
Other Libraries in Japan

Rev 2 to GENE-B13-01920-63, "Evaluation of NMP Unit 2 Shroud Cracking For At Least One FC of Operation Following RF06."

Rev 2 to GENE-B13-01920-63, "Evaluation of NMP Unit 2 Shroud Cracking For At Least One FC of Operation Following RF06."
Paper図書
CAINE, T. A.//MEHTA, H. S.//STARK, R. R.GENERAL ELECTRIC CO.1998/06/30.
Other Libraries in Japan

"Evaluation to Determine Limiting Operating Condition in BFN III RPV Flaw Handbook."

"Evaluation to Determine Limiting Operating Condition in BFN III RPV Flaw Handbook."
Paper図書
MEHTA, H. S.//RANGANATH, S.GENERAL ELECTRIC CO.1995/11/30.
Other Libraries in Japan

Non-proprietary version of Rev 1 to GE-NE-523-B13-01869-043, "Assessment of Vertical Weld Cracking on NMP1 Shroud."

Non-proprietary version of Rev 1 to GE-NE-523-B13-01869-043, "Assessment of Vertical Weld Cracking on NMP1 Shroud."
Paper図書
CHOE, H.//MEHTA, H. S.//RANGANATH, S.GENERAL ELECTRIC CO.1997/04/30.
Other Libraries in Japan

Non-proprietary Rev 0 to GE-NE-523-B13-01869-043, "Assessment of Vertical Weld Cracking on NMP1 Shroud."

Non-proprietary Rev 0 to GE-NE-523-B13-01869-043, "Assessment of Vertical Weld Cracking on NMP1 Shroud."
Paper図書
CHOE, H.//MEHTA, H. S.//RANGANATH, S.GENERAL ELECTRIC CO.1997/04/30.
Other Libraries in Japan

"Environ Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel & Piping Fatigue Evaluations," final rept.

"Environ Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel & Piping Fatigue Evaluations," final rept.
Paper図書
GOSSELIN, S. R.//MEHTA, H. S.ELECTRIC POWER RESEARCH INSTITUTE,GENERAL ELECTRIC CO.1995/12/31.
Other Libraries in Japan

Rev 1 to GE-NE-B13-01805-22, "Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3."

Rev 1 to GE-NE-B13-01805-22, "Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3."
Paper図書
DANIEL, R.//MEHTA, H. S.//STARK, R.GENERAL ELECTRIC CO.1997/01/31.
Other Libraries in Japan

Suppl 1 to GE-NE-B13-01739-04, "Nine Mile Unit 1 Shroud."

Suppl 1 to GE-NE-B13-01739-04, "Nine Mile Unit 1 Shroud."
Paper図書
HERRERA, M. L.//MEHTA, H. S.GENERAL ELECTRIC CO.1995/02/24.
Other Libraries in Japan

Rev 0 to "Evaluation of Hatch Unit 1 Shroud Vertical Weld Indications."

Rev 0 to "Evaluation of Hatch Unit 1 Shroud Vertical Weld Indications."
Paper図書
LAI, W.//MEHTA, H. S.//RANGANATH, S.GENERAL ELECTRIC CO.1996/04/30.
Other Libraries in Japan