Use of master curve technology for assessing shallow flaws in a reactor pressure vessel material
, 2022 Art. 031407, 11 S.In the NESC-IV project, an experimental/analytical program was performed to develop validated analysis methods for transferring fracture toughness data to shallow flaws in reactor pressure vessels subject to biaxial loading in the lower-
Wintle, J. +6 more
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Design by analysis of ductile failure and buckling in torispherical pressure vessel heads [PDF]
, 2008 Thin shell torispherical pressure vessel heads are known to exhibit complex elastic-plastic deformation and buckling behaviour under static pressure. In pressure vessel Design by Analysis, the designer is required to assess both of these behaviour modes ...
Camilleri, Duncan +2 more
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, 1989 Corrosion fatigue crack growth rate of Soviet reactor pressure vessel steel 15X2M∅A and its cladding were studied in simulated PWR-conditions. The crack growth rate was highest in the cladding and lowest near the fusion line.
Fedorova, V. +6 more
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Burst pressure of super duplex stainless steel pipes subject to combined axial tension, internal pressure and elevated temperature [PDF]
, 2014 Peer ...
Akisanya, A. R., Lasebikan, B. A.
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Simulation of the influence of hydrophones used for the characterization of pressure field distribution in low frequency, high power ultrasonic reactor vessels [PDF]
, 2007 This paper describes the use of a finite element (FE) modeling approach to investigate the influence of different hydrophone designs in laboratory scale reactor vessels.
O'Leary, R.L., Harvey, G., Gachagan, A.
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Validation of RT(T0) for German reactor pressure vessel steels
, 2022 Art. 031405, 6 S.For the introduction of the new reference temperature RTT0 of the ASME Code Cases N-629 and N-631 into the German Standard KTA 3201.2, the applicability of RTT0 was validated by the reevaluation of the existing fracture toughness ...
Keim, E., Siegele, D., Nagel, G.
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Probabilistic pressurized thermal shocks analyses for a reactor pressure vessel
, 2015 Both deterministic and probabilistic methods are used to assess the integrity of a reactor pressure vessel (RPV) subjected to pressurized thermal shocks (PTSs).
Qian, Guian (author) +1 more
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Modelling thermal effects in agitated vessel and reactor design consideration [PDF]
, 2007 The knowledge of the heat transfer coefficient on the inner side of a heated vessel wall is of utmost importance for the design of agitated vessels. The present contribution deals with heat transfer in an agitated vessel containing non-Newtonian liquid ...
Chergui, Nacera +3 more
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Characterising plastic collapse of pipe bend structures [PDF]
, 2006 Two recently proposed design by analysis criteria of plastic collapse based on plastic work concepts, the plastic work (PW) criterion and the plastic work curvature (PWC) criterion, are applied to a strain hardening pipe bend arrangement subject to ...
Li, Hongjun, Mackenzie, Donald
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UK Rules For Unfired Pressure Vessels [PDF]
, 2008 The present code PD 5500, formerly BS 5500 [1] evolved partly from the well-known BS 1500 [2] in the 1950's and BS 1515 [3] first published in 1965; the latter permitted higher level allowable stresses and more advanced rules. In 1969, following a report
Nash, David H.
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