Pascal and Francis Bibliographic Databases

Help

Search results

Your search

kw.\*:("Reactor pressure vessel")

Document Type [dt]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Publication Year[py]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Discipline (document) [di]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Language

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Author Country

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Results 1 to 25 of 416

  • Page / 17
Export

Selection :

  • and

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

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

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

A CALCULATION-EXPERIMENTAL STUDY OF CRACK-TIP OPENING DISPLACEMENT AND RESIDUAL STRESSES UPON WARM PRESTRESSINGPOKROVSKII, V. V; SIDYACHENKO, V. G; EZHOV, V. N et al.Strength of materials. 2011, Vol 43, Num 1, pp 56-65, issn 0039-2316, 10 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

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

Measurement of the Young modulus anisotropy of a reactor pressure vessel claddingVANDERMEULEN, W; SCIBETTA, M; LEENAERS, A et al.Journal of nuclear materials. 2008, Vol 372, Num 2-3, pp 249-255, issn 0022-3115, 7 p.Article

Numerical prediction of cooling margins for a fluid with internal heat generationHORVAT, A; KLJENAK, I; MARN, J et al.International conference on advanced computational methods in heat transfer. 1998, pp 337-346, isbn 1-85312-591-1Conference Paper

CORVIS. Investigation of light water reactor lower head failure modesBROSI, S; DUIJVESTIJN, G; HIRSCHMANN, H et al.Nuclear engineering and design. 1997, Vol 168, Num 1-3, pp 77-104, issn 0029-5493Article

Effect of cladding on the initiation behaviour of finite length cracks in an RPV under thermal shockBLAUEL, J. G; HODULAK, L; NAGEL, G et al.Nuclear engineering and design. 1997, Vol 171, Num 1-3, pp 179-188, issn 0029-5493Conference Paper

Magnetic properties of a highly neutron-irradiated nuclear reactor pressure vessel steelKOBAYASHI, S; GILLEMOT, F; HORVATH, A et al.Journal of nuclear materials. 2012, Vol 421, Num 1-3, pp 112-116, issn 0022-3115, 5 p.Article

Creep Effects on Design Below the Temperature Limits of ASME Section III Subsection NBSHAM, T.-L; JETTER, Robert I; ENO, Daniel R et al.Journal of engineering for gas turbines and power. 2010, Vol 132, Num 1, issn 0742-4795, 012904.1-012904.6Article

  • Page / 17