Results 61 to 70 of about 2,093 (208)
Archives of Control Sciences, 2015 In the paper, analysis of multi-region fuzzy logic controller with local PID controllers for steam generator of pressurized water reactor (PWR) working in wide range of thermal power changes is presented.
Puchalski Bartosz +2 more
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Investigation on reverse flow characteristics in U-tubes under two-phase natural circulation
Nuclear Engineering and Technology, 2020 The vertically inverted U-tube steam generator (UTSG) is widely used in the pressurized water reactor (PWR). The reverse flow behavior generally exists in some U-tubes of a steam generator (SG) under both single- and two-phase natural circulations (NCs).
Xi Chu +3 more
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Circumferential cracking of steam generator tubes [PDF]
, 1997 On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-03, {open_quote}Circumferential Cracking of Steam Generator Tubes.{close_quote} GL 95-03 was issued to obtain information needed to verify licensee compliance with existing regulatory requirements regarding the integrity of steam generator tubes in domestic ...
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Steam generator tube rupture study [PDF]
, 1986 This report describes our investigation of steam generator behavior during a postulated tube rupture accident. Our study was performed using the steam generator, thermal-hydraulic analysis code THERMIT-UTSG.
Free, Scott Thomas, Schor, Andrei L.
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The Fretting Wear Characteristics of CrN and TiN Coating on Steam Generator Tube [PDF]
, 2010 A steam generator tube of a nuclear power plant is damaged by a fretting phenomenon caused by flow induced vibrations (FIV). In this work, the surface of the tube was coated with CrN or TiN as a measure to improve performance of the fretting wear ...
Jin-Seon Kim +2 more
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Condition-based probabilistic safety assessment of a spontaneous steam generator tube rupture accident scenario [PDF]
, 2018 Condition-Based Probabilistic Safety Assessment (CB-PSA) makes use of the information made available during operation by sensors and/or inspections on the state of components and systems.
ANTONELLO, FEDERICO +5 more
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Nuclear Engineering and Technology, 2019 This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage ...
Ji-Seok Kim +3 more
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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 ...
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Dynamic Sliding Mode Control of Nuclear Steam Generators Using Out-Put Feedback Based on a Nonlinear Model [PDF]
مجله علوم و فنون هستهای, 2013 U-Tube Steam Generator (UTSG) is a crucial component in nuclear power plant with the pressurized-water reactor. Ineffective control of the Steam Generator (SG) water level in the secondary circuit of a nuclear power plant can lead to frequent reactor ...
G.R Ansarifar, H.A Talebi
doaj
CFD simulation of steam generator tube rupture thermal-hydraulics [PDF]
, 2004 The tube rupture accident is one among the most risk-dominant events at the nuclear power plants. Several steam generator tube rupture accidents have occurred at the plants in the past.
Maslovarić, Blaženka +3 more
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