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International Association for Structural Mechanics in Reactor Technology (IASMiRT)
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Showing items 1-13 of 13

A Study of Simplified Fatigue Evaluation Method Based on Operating Data

Yuji Takahashi; Yuichi Okamura; Yasuchi Kanazawa; Naoki Kojima (IASMiRT, 1999-08-15)
Cracking behavior and positron annihilation measurement during fatigue damage in austenitic stainless steel

N. Nakamura; M. Uchida; C. Fukuoka; K. Yoshida (IASMiRT, 1997-08-17)
Establishment of Simplified Fatigue Evaluation Method by Green's Function

Hideki Fujimoto; Yasushi Kanazawa; Yuji Takahashi (IASMiRT, 1999-08-15)
Evaluation of plastic deformation in austenitic stainless steel by positron annihilation

N. Nakamura; M. Uchida; K. Yoshida; M. Takimoto (IASMiRT, 1997-08-17)
Fatigue Analysis of Modified Main-Steam Isolation Valve for Yonggwang Nuclear Units 1 & 2

Due Yule Chung; Tae Soo Hahn; Weon Seo Park (IASMiRT, 1999-08-15)
Improvement of residual stress on material surface by water jet peening

K. Hirano; K. Enomoto; M. Mochizuki; M. Hayashi; E. Hayashi; S. Shimizu (IASMiRT, 1997-08-17)
Latest Advances in Fatigue Monitoring Technology Using EPRI's FatiguePro Software

Gary L. Stevens; David A. Gerber; Stan T. Rosinski (IASMiRT, 1999-08-15)
Maintenance of Major Edf Components

Bacot, J. (IASMiRT, 1995-08-13)
Reactor pressure vessel annealing demonstration evaluation

W.E. Pennell; B.R. Bass; J.A. Keeney; C.B. Oland; L.J. Ott; S.N. Malik; M.A. Mitchell (IASMiRT, 1997-08-17)
Reactor pressure vessel annealing-effective mitigation method

M. Brumovsky; J. Brynda (IASMiRT, 1997-08-17)
Test results of aged cast austenitic stainless steel elbows

S. Sahgal; T.R. Mager; C.C. Kim; D.C. Bhowmick (IASMiRT, 1997-08-17)
Thermal Fatigue in Piping Tees - Cost Effective Methods for Assessment

Urs Blumer; Daniels Humair (IASMiRT, 1999-08-15)
Thermal Loading Phenomena and Monitoring for Material Fatigue in Nuclear Power Plants

H. J. Golembiewski; W. Kleinoeder (IASMiRT, 1999-08-15)

Showing items 1-13 of 13