Results 41 to 50 of about 867,433 (284)

Study on the Distribution Characteristics of Aerosol Particle Released From Solution Leakage: Based on Solution Temperature Variation

Asia-Pacific Journal of Chemical Engineering, EarlyView.
ABSTRACT A simulation experimental device was established and utilized to study the phenomenon of solution leakage in nuclear fuel cycle facilities. The particle size and concentration distribution of aerosols released from solution leakage were investigated at different temperatures using ELPI and LPSA.
Zhi Zhang, Yiren Lian, Shutang Sun, Yeming Zhu, Jin Yan, Jiangyu Niu, Shiqi Zhang, Haoming Dou, Hongchao Sun, Guoqiang Li, Yanlong Qi   +10 more
wiley   +1 more source

Markov stochastic process modeling for evolution of wear depth in steam generator tubes

Advances in Mechanical Engineering, 2019
Reliability of steam generator is a serious concern in the operation of nuclear power plants, especially for steam generator tubes that experience a variety of degradation mechanisms including wear damage. It is necessary to develop a model to accurately
Xing He, Xiaojiao Xu, Wei Tian, Yuebing Li, Weiya Jin, Mingjue Zhou   +5 more
doaj   +1 more source

Fiber Fabry-Perot Force Sensor with Small Volume and High Performance for Assessing Fretting Damage of Steam Generator Tubes

Sensors, 2017
Measuring the radial collision force between the steam generator tube (SGT) and the tube support plate (TSP) is essential to assess the fretting damage of the SGT. In order to measure the radial collision force, a novel miniaturized force sensor based on
Peijian Huang, Ning Wang, Junying Li, Yong Zhu, Jie Zhang   +4 more
doaj   +1 more source

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.
core  

Steam generator tube integrity program. Phase I report. [PWR] [PDF]

, 1979
The results are presented of the pressure tests performed as part of Phase I of the Steam Generator Tube Integrity (SGTI) program at Battelle Pacific Northwest Laboratory.
Alzheimer, J. M., Clark, R. A., Vagins, M., Morris, C. J.   +3 more
core   +1 more source

Thermophilic anaerobic treatment and biogas generation from wastewater produced in an advanced biorefinery process

Biofuels, Bioproducts and Biorefining, EarlyView.
Abstract Anaerobic digestion can be an alternative method for treating wastewater from second‐generation biorefineries while simultaneously producing biogas. However, the feasibility of the process and key operational parameters by which wastewater produced in lignocellulosic biorefineries affects reactor performance remain poorly understood.
Jairo M. Carrillo‐Osorio, Germán Buitrón   +1 more
wiley   +1 more source

Clinch River Breeder Reactor Plant steam generator: FEW tube test model post test examination [PDF]

, 1979
The Steam Generator Few Tube Test (FTT) is part of an extensive testing program being carried out in support of the Clinch River Breeder Reactor Plant (CRBRP) steam generator design.
Impellezzeri, J. R., Camaret, T. L.
core  

Low‐Field MRI as a Multiparametric Tool for Large Engineered Tissue Characterization

Biotechnology and Bioengineering, EarlyView.
ABSTRACT Advances in 3D bioprinting have enabled the fabrication of large and complex engineered tissues, but their increasing size demands non‐invasive tools for monitoring structure, maturation, and perfusion. Magnetic Resonance Imaging (MRI) offers unique multiparametric capabilities, yet high‐field systems remain costly and inaccessible for most ...
Yilbert Gimenez, Valernst Martial Gilmus, Elliott Cowles, Lucie Essayan, Vincent Semet, Michel Cabrera, Christophe A. Marquette, Simon A. Lambert, Emma Petiot   +8 more
wiley   +1 more source

Investigation of the Impact of Changing the Heat Exchange Area on PHV-1000 Steam Generator Productivity

Energy Engineering and Control Systems
The PHV-1000 steam generator is one of the main heat exchangers in the primary circuit of the power unit of nuclear power plants with a WWER-1000 reactor.
Marta Kuznetsova, Halyna Matiko, Oleksandr Liashyk   +2 more
doaj   +1 more source

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 ...
openaire   +2 more sources