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

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

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

Tensile properties and internal friction study of dislocation movement in iron-copper system as a function of copper precipitationKONSTANTINOVIC, M. J; ALMAZOUZI, A; SCIBETTA, M et al.Journal of nuclear materials. 2007, Vol 362, Num 2-3, pp 283-286, issn 0022-3115, 4 p.Conference Paper

The design of the J-type neutron flux distribution measurement systemLUO ZHENGPEI; LI FU; WANG YA QI et al.Nuclear engineering and design. 1999, Vol 194, Num 2-3, pp 179-184, issn 0029-5493Article

SMiRT-14 Post Conference Seminar No 4. Containment of Nuclear ReactorsKRIEG, R; HUBER, A; PFEIFFER, P. A et al.Nuclear engineering and design. 1999, Vol 191, Num 1, issn 0029-5493, 101 p.Serial Issue

New observations on the crack growth rate of low alloy nuclear grade ferritic steels under constant active load in oxygenated high-temperature waterKUSSMAUL, K; BLIND, D; LÄPPLE, V et al.Nuclear engineering and design. 1997, Vol 168, Num 1-3, pp 53-75, issn 0029-5493Article

The ASYNT adjoint synthesis method for neutron irradiation assessment of VVER/pressurized water reactor pressure vesselBELOUSOV, S. I; ILIEVA, K. D.Nuclear science and engineering. 1997, Vol 126, Num 2, pp 239-244, issn 0029-5639Article

The application of mechanical and thermal cutting tools for the dismantling of activated internals of the reactor pressure Vessels in the versuchsatomkraftwerk, Kahl and the Gundremmingen Unit AEICKELPASCH, N; KALWA, H; STEINER, H et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 175-182, issn 0029-5493Conference Paper