Results 41 to 50 of about 52,055 (257)
As a critical component of nuclear and thermal energy conversion systems, the long-term safe operation of a steam generator depends on the structural integrity of its tube bundles.
Yuhua Hang +6 more
doaj +1 more source
The purpose of this research is to introduce the technical standard of accident sequence precursor (ASP) analysis, and to propose a case study using the dynamic-probabilistic safety assessment (D-PSA) approach.
Hansul Lee, Taewan Kim, G. Heo
semanticscholar +1 more source
Data analysis for steam generator tubing samples [PDF]
The objective of the Improved Eddy-Current ISI for Steam Generators program is to upgrade and validate eddy-current inspections, including probes, instrumentation, and data processing techniques for inservice inspection of new, used, and repaired steam generator tubes; to improve defect detection, classification and characterization as affected by ...
openaire +3 more sources
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
doaj +1 more source
Investigation on reverse flow characteristics in U-tubes under two-phase natural circulation
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
doaj +1 more source
Steam generator tube denting simulation testing. [PWR] [PDF]
Tube denting has been reported in steam generators in a number of commercial nuclear power plants in recent years. In order to aid in understanding of the mechanism leading to tube denting in the steam generators, a Bettis laboratory test program was initiated to attempt to reproduce tube denting and to investigate the effects of chemistry, design, and
Battaglia, P. J., Singley, W. J.
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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
doaj +1 more source
Dynamic Sliding Mode Control of Nuclear Steam Generators Using Out-Put Feedback Based on a Nonlinear Model [PDF]
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
Performance Analysis and Tube Inlet Orifice Length Evaluation of a Once–Through Steam Generator [PDF]
A numerical study is conducted for performance analysis and secondary side screw-type tube inlet orifice design of a once–through steam generator (OTSG).
Sik Han Hun +5 more
doaj +1 more source
Circumferential cracking of steam generator tubes [PDF]
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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