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Results 1 to 25 of 672

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Development of an integrity evaluation system for nuclear power plantsKIM, Young-Jin; CHOI, Jae-Boong; LEE, Joon-Seong et al.JSME international journal. Series C, Mechanical systems, machine elements and manufacturing. 2003, Vol 46, Num 4, pp 1464-1472, issn 1344-7653, 9 p.Article

Assessment of the master curve approach on three reactor pressure vessel steelsLUCON, Enrico; SCIBETTA, Marc; VAN WALLE, Eric et al.International journal of fracture. 2003, Vol 119, Num 2, pp 161-178, issn 0376-9429, 18 p.Article

Comparative study of irradiated and hydrogen implantation damaged German RPV steels from PAS point of viewPECKO, Stanislav; SOJAK, Stanislav; SLUGEN, Vladimír et al.Applied surface science. 2014, Vol 312, pp 172-175, issn 0169-4332, 4 p.Article

Evolution of design methodologies for next generation of reactor pressure vessels and extensive role of thermal-hydraulic numerical toolsBELLET, Serge; GOREAUD, Nicolas; NICAISE, Norbert et al.Nuclear technology. 2005, Vol 152, Num 2, pp 196-209, issn 0029-5450, 14 p.Conference Paper

Irradiation temperature, flux and spectrum effectsBALLESTEROS, A; AHLSTRAND, R; BRUYNOOGHE, C et al.Progress in nuclear energy (New series). 2011, Vol 53, Num 6, pp 756-759, issn 0149-1970, 4 p.Article

A kinetics study of vacancy cluster evolution under VVER-type reactor conditionGOKHMAN, A; BOEHMERT, J.Radiation effects and defects in solids. 2003, Vol 158, Num 7, pp 499-511, issn 1042-0150, 13 p.Article

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel SteelsSONEDA, Naoki; NOMOTO, Akiyoshi.Journal of engineering for gas turbines and power. 2010, Vol 132, Num 10, issn 0742-4795, 102918.1-102918.9Article

LOCAL APPROACH TO FRACTURE-BASED PREDICTION OF REACTOR PRESSURE VESSEL LIFETIMEKOTRECHKO, S. A; MESHKOV, Yu. Ya.Strength of materials. 2009, Vol 41, Num 1, pp 39-44, issn 0039-2316, 6 p.Conference Paper

ANALYSIS OF WARM PRESTRESSING EFFECT ON FRACTURE TOUGHNESS OF REACTOR PRESSURE VESSEL STEELSBELEINAI, R; SZAVAI, Sz.Strength of materials. 2010, Vol 42, Num 1, pp 120-123, issn 0039-2316, 4 p.Conference Paper


Probabilistic Fracture Mechanics Round Robin Analysis of Reactor Pressure Vessels during Pressurized Thermal ShockJHUNG, Myung Jo; SEOK HUN KIM; YOUNG HWAN CHOI et al.Journal of nuclear science and technology. 2010, Vol 47, Num 12, pp 1131-1139, issn 0022-3131, 9 p.Article

Interaction of a screw dislocation with Cu-precipitates, nanovoids and Cu-vacancy clusters in BCC ironTERENTYEV, Dmitry; MALERBA, Lorenzo.Journal of nuclear materials. 2012, Vol 421, Num 1-3, pp 32-38, issn 0022-3115, 7 p.Article

Prediction of radiation induced hardening of reactor pressure vessel steels using artificial neural networksCASTIN, N; MALERBA, L; CHAOUADI, R et al.Journal of nuclear materials. 2011, Vol 408, Num 1, pp 30-39, issn 0022-3115, 10 p.Article

Radiation induced hardening of ion irradiated RPV steelsWATANABE, H; MASAKI, S; MASUBUCHI, S et al.Journal of nuclear materials. 2011, Vol 417, Num 1-3, pp 932-935, issn 0022-3115, 4 p.Conference Paper

On the validity of the cluster model to describe the evolution of Cu precipitates in Fe-Cu alloysGOLUBOV, S. I; SERRA, A; OSETSKY, Yu. N et al.Journal of nuclear materials. 2000, Vol 277, Num 1, pp 113-115, issn 0022-3115Article

Innovative Prüfsysteme für Reaktordruckbehälter : Über das Für und Wider einer neuen Technik = DELPHIN : a new system for testing reactor pressure vesselsDRESSLER, K.Atw. Internationale Zeitschrift für Kernenergie. 1999, Vol 44, Num 6, issn 1431-5254, 341, 369-371 [4 p.]Article

Wirtschaftlicher Rückbau von Kernreaktoren = Economical dismantling of nuclear power stationsMALLOK, J; ANDERMANN, H.Atw. Internationale Zeitschrift für Kernenergie. 1999, Vol 44, Num 10, issn 1431-5254, 464, 481-484 [5 p.]Article

Underwater inspection robot-AIRIS 21®KOJI, K.Nuclear engineering and design. 1999, Vol 188, Num 3, pp 367-371, issn 0029-5493Article

Einsatz innovativer Techniken zur Prüfzeitreduzierung = Employing innovative techniques to reduce inspection timesHEUMÜLLER, R; GUSE, G; DIRAUF, F et al.Atw. Atomwirtschaft, Atomtechnik. 1997, Vol 42, Num 3, pp 173-176, issn 0365-8414Article

Results of examinations of pressure vessel samples and instrument nozzles from the TMI-2 lower headKORTH, G. E; DIERCKS, D. R; NEIMARK, L. A et al.Nuclear engineering and design. 1997, Vol 167, Num 3, pp 267-285, issn 0029-5493Article

ASYNT-an adjoint synthesis method for neutron irradiation estimation on the vessels of VVER/PWR reactorsBELOUSOV, S. I; ILIEVA, K. D.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 27-33, issn 0029-5493Conference Paper

Studies for the staggered pans core catcherFIEG, G; MÖSCHKE, M; WERLE, H et al.Nuclear technology. 1995, Vol 111, Num 3, pp 331-340, issn 0029-5450Article

Application of GTAW welding robots to nozzels of reactor pressure vesselsYAMADORI, H; TAKEDA, H; WATANABE, S et al.Ishikawajima-Harima Giho. 1999, Vol 39, Num 1, pp 24-28, issn 0578-7904Article

Examination of the materials from operating wwer pressure vesselsSHTROMBAKH, Ya; KRYUKOV, A; PLATONOV, P et al.Fontevraud. Colloque international. 1998, pp 45-60, 2VolConference Paper

Investigation of ALPHA experiment by severe accident analysis code SAMPSONBAGLIETTO, Emilio; NINOKATA, Hisashi; NAITOH, Masanori et al.Nuclear engineering and design. 2008, Vol 238, Num 7, pp 1561-1568, issn 0029-5493, 8 p.Article

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