Results 11 to 20 of about 867,433 (284)
Steam generator tube failures [PDF]
, 1996 A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation ...
MacDonald, P. E. +3 more
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Thermal Hydraulic Modeling of Once-Through Steam Generator by Two-Fluid U-Tube Steam Generator Code [PDF]
Atom Indonesia, 2017 The THERMIT U-tube steam generator (THERMIT-UTSG) code was used for evaluation for the parametric study of a scaled once-through pressurized water reactor steam generator (OTSG) made by Babcock & Wilcox.
A. Zeighami +3 more
doaj +7 more sources
LMFBR steam generator development: duplex bayonet tube steam generator. Volume II [PDF]
, 1975 This report represents the culmination of work performed in fulfillment of ERDA Contract AT(11-1)-2426, Task Agreement 2, in which alternate steam generator designs were developed and studied. The basic bayonet tube generator design previously developed by C-E under AEC Contract AT(11-1)-3031 was expanded by incorporating duplex heat transfer tubes to ...
DeFur, D. D.
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Steam generator tube rupture (SGTR) scenarios
Nuclear Engineering and Design, 2005 The steam generator tube rupture (SGTR) scenarios project was carried out in the EU 5th framework programme in the field of nuclear safety during years 2000–2002. The first objective of the project was to generate a comprehensive database on fission product retention in a steam generator. The second objective was to verify and develop predictive models
Auvinen, A. +13 more
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Steam generator tube rupture scenarios (SGTR)
, 2003 The Steam Generator Tube Rupture (SGTR) scenarios project was carried out in the framework of the research and training programme, EURATOM, in the field of nuclear energy during years 2000-2002.
Lähde, Anna +14 more
core +3 more sources
Steam Generator Secondary pH during a Steam Generator Tube Rupture [PDF]
Nuclear Technology, 1993 The Nuclear Regulatory Commission requires utilizes to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the partitioning of iodine between liquid and vapor in steam generator secondary.
James P. Adams, Eric S. Peterson
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Description of a model of a U-tube steam generator [PDF]
, 1973 The report describes a one-dimensional model of a U-tube steam generator. The-main emphasis is placed on the derivation of the equations and a discursion of theproblem arising by a pure digital and a hybrid solution. Only a few results are included.
Christensen, P. la Cour
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Failure Analysis of Steam Generator Tubes
, 2023 Steam generator fabricated of alloy 600 tubes has been replaced in the last decades by newer versions built with alloy 690 or alloy 800 tubes. At first, it was thought that both alloys were resistant to SCC mechanisms but after several years of operation, some NPPs developed denting processes and IGSCC, especially in alloy 800.
Diego, Gonzalo, Merino, Susana
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Reliability of Degraded Steam Generator Tubes [PDF]
, 2011 Steam generators in the second generation nuclear power plants with pressurized water and CANDU reactors were in most cases of the shell-and-tube type. The reactor coolant passes through the tubes at the primary side and boils water on the outside of the tubes (secondary shell side) to make steam.
Leon Cizelj, Guy Roussel
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Steam generator tube integrity program
Nuclear Engineering and Design, 1996 Abstract The degradation of steam generator tubes in pressurized water nuclear reactors continues to be a serious problem, and the US Nuclear Regulatory Commission (NRC) is developing a performance-based rule and regulatory guide for steam generator tube integrity.
D.R. Diercks, J. Muscara, W.J. Shack
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