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

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

The toughness module of the PERFECT platform: A predictive tool for the fracture toughness of RPV steelsBUGAT, S; EL GHARIB, J; PROIX, J.-M et al.Journal of nuclear materials. 2010, Vol 406, Num 1, pp 187-192, issn 0022-3115, 6 p.Article

Developing a generalized flaw distribution for reactor pressure vesselsJACKSON, Deborah A; DOCTOR, Steven R; SCHUSTER, George et al.Nuclear engineering and design. 2001, Vol 208, Num 2, pp 123-131, issn 0029-5493Conference Paper

Positron lifetime study of reactor pressure vessel steelsCIZEK, J; PROCHAZKA, I; KOCIK, J et al.Physica status solidi. A. Applied research. 2000, Vol 178, Num 2, pp 651-662, issn 0031-8965Article

Uniform gauss-weight quadratures for discrete ordinate transport calculationsCAREW, John F; KAI HU; ZAMONSKY, Gabriel et al.Nuclear science and engineering. 2000, Vol 136, Num 2, pp 282-293, issn 0029-5639Article

Structural integrity assessment of aging nuclear reactor pressure vesselsPENNELL, W. E; MALIK, S. N. M.Nuclear engineering and design. 1997, Vol 172, Num 1-2, pp 27-47, issn 0029-5493Article

Three-dimensional damage theory of crack growth in large centre-cracked panels using the element removal techniqueLI, Z. H; HOWARD, I. C; BILBY, B. A et al.Nuclear engineering and design. 1997, Vol 172, Num 1-2, pp 1-12, issn 0029-5493Article

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

Heavy DutyMINTZ TESTA, Bridget.Mechanical engineering (New York, N.Y. 1919). 2012, Vol 134, Num 4, issn 0025-6501, 28-32 [4 p.]Article