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Proceedings
International Association for Structural Mechanics in Reactor Technology (IASMiRT)
2005 - SMiRT 18 - Beijing, China
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Now showing items 1-20 of 32

Ageing Management Database Development for PWR NPP Steam Generator

Hongyun Liu; Liangjun Xu; Changhuai Xiong; Xianyuan Wang (IASMiRT, 2005-08-07)
Ageing Management of Nuclear Components: A Safety and Economical Issue

Claude Faidy (IASMiRT, 2005-08-07)
Aging Management of PWR Internals Components

H.T. Tang; Jeff D. Gilreath (IASMiRT, 2005-08-07)
An Approach for Low Cycle Fatigue Life Prediction of Various Metallic Materials Subjected to Non-Proportional Multiaxial Loading

Haisheng Yu; S.N. Shukayev (IASMiRT, 2005-08-07)
Application of System Dialife for Residual Life Time Assessment on Nuclear Power Plant Components

Dusan Vincour; Ladislav Jurasek (IASMiRT, 2005-08-07)
Comparison between S-N-P Curves Obtained from Constant Stress and Step-Stress Fatigue Tests

João Mário Andrade Pinto; Tanius Rodrigues Mansur; Miguel Mattar Neto; Enrico Antonio Colosimo (IASMiRT, 2005-08-07)
Control of Selected VVER Components Life Time SKODA JS a.s. Experience

Jan Zdebor; Eugen Pribulla (IASMiRT, 2005-08-07)
Corrosion Monitoring Programmes for Life Time Extension of NPP Components

Martin Brezina; Ludovit Kupca; Peter Beno (IASMiRT, 2005-08-07)
Development of the Normative Documentation for Control Exploitation Pipe Lines of Second Side NPP with VVER

V.I. Baranenko; S.G. Oleynik; O.A. Belyakov; R.S. Istomin; A.V. Kumov (IASMiRT, 2005-08-07)
Evaluation of Environmental Fatigue Lifetime for Nuclear Welded Structure Based on Structural Stress and Fracture Mechanics Approach

Jong-Sung Kim; Tae-Eun Jin (IASMiRT, 2005-08-07)
Experience of Operating the Automatic System of Residual Service Life Monitoring for WWER-1000

A.V. Bogachev; B.N. Dranchenko; V.P. Semishkin; M.B. Bakirov (IASMiRT, 2005-08-07)
Flux Effect on Radiation Embrittlement of VVER-440 Reactor Pressure Vessel Materials

Alexandr Kryukov; Anna Chernobaeva; Amir Amaev; Dmitry Erak; Pavel Platonov; Yaroslav Shtrombakh (IASMiRT, 2005-08-07)
French Nuclear Plant Life Management Strategy Application on Reactor Pressure Vessels and Steam Generators Life Management

Georges Bezdikian (IASMiRT, 2005-08-07)
Have Any Material Tests Been Forgotten?

Josef Jansky (IASMiRT, 2005-08-07)
High Cycle Thermal Crazing: a Phenomena Related to the Structure

Said Taheri; Erwan Galenne (IASMiRT, 2005-08-07)
Integrated Plant Life Management (PLiM) - The IAEA Contribution

Ki-Sig Kang; Claude Russell Clark; Akira Omoto (IASMiRT, 2005-08-07)
Integrated Surveillance Specimen Program for WWER-1000/V-320 Reactor Pressure Vessels

Milan Brumovsky; Milo Kytka; Petr Novosad; Jiri ZDárek (IASMiRT, 2005-08-07)
Integrity Assessment Technology for the Aging Management

Tae-Eun Jin (IASMiRT, 2005-08-07)
Key Elements of the Ageing Management of the WWER-440/213 Type Nuclear Power Plants

Tamás János Katona; Ágnes Jánosiné Bíró; Sándor Rátkai; Zoltán Ferenczi (IASMiRT, 2005-08-07)
Life-Time Prediction of Austenitic Stainless Steel by Applying Magnetic NDT-Methods

Markus Niffenegger; Hans J. Leber; Dietmar Kalkhof (IASMiRT, 2005-08-07)

Now showing items 1-20 of 32