Results 11 to 20 of about 36,185 (292)

Micro-Galvanic Corrosion of Steam Generator Materials within Pores of Magnetite Flakes in Alkaline Solutions

Metals, 2018
In secondary coolant system of the pressurized water reactors, the reduced corrosion products such as metallic Cu and Pb particles were accumulated in the pores of the magnetite flakes and electrically contacted to the steam generator materials.
Soon-Hyeok Jeon, Geun Dong Song, Do Haeng Hur   +2 more
doaj   +1 more source

Pre-test analysis of protected loss of primary pump transients in CIRCE-HERO facility [PDF]

, 2017
In the frame of LEADER project (Lead-cooled European Advanced Demonstration Reactor), a new configuration of the steam generator for ALFRED (Advanced Lead Fast Reactor European Demonstrator) was proposed. The new concept is a super-heated steam generator,
Caruso, G., Del Nevo, A, Giannetti, F, Narcisi, V, Tarantino, M   +4 more
core   +1 more source

Experimental investigation of heat and mass exchange processes during operation of VVER steam generator in emergency condensing mode

Nuclear Energy and Technology, 2017
GE2M-PG test facility was constructed at the JSC “SSC RF-IPPE” for assessment of efficiency of VVER steam generator and investigation of effects of initial conditions of the accident on the processes of heat exchange in the steam generator (SG) tube ...
A.S. Shlyopkin, A.V. Morozov, D.S. Kalyakin, A.S. Soshkina   +3 more
doaj   +1 more source

Numerical Study on the Effect of Deposit Layer on the Minimum Wall Thickness of Boiler Water Tube under Different Operating Conditions

Applied Sciences, 2022
Water wall tube temperature is a major parameter in the steam generator design which has a significant role in keeping the steam generator available. Thus, knowing the tube average temperature in different operating conditions is very important to avoid ...
Ahmed S. Aljohani, Khaled I. Ahmed, Saeed Asiri, Mohamed H. Ahmed   +3 more
doaj   +1 more source

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
openaire   +2 more sources

Identification of magnetic deposits in 2-D axisymmetric eddy current models via shape optimization [PDF]

, 2015
International audienceThe non-destructive control of steam generators is an essential task for the safe and failure-free operation of nuclear power plants.
El-Guedri, Mabrouka, Haddar, Houssem, Jiang, Zixian, Lechleiter, Armin   +3 more
core   +3 more sources

Thermal-hydraulic Characteristics Analysis Method of Helical Coil Steam Generator in High Temperature Gas Reactor

Yuanzineng kexue jishu, 2022
High temperature gas reactors (HTGRs) have broad application prospects in power supply, seawater desalination and hydrogen production. Helical coil steam generators have the advantages of compact structure, high heat transfer efficiency and resistance to
WANG Mingjun;SUN Jinxiang;ZHANG Jing;TIAN Wenxi;QIU Suizheng;SU Guanghui
doaj  

Research on the Thermal Stratification Phenomenon at the Secondary Side of a Steam Generator in an Isolated Loop

Energies, 2022
In normal operation, there is no significant thermal stratification phenomenon in the tube bundle area of the steam generator of the nuclear power plant.
Xinxin Liu, Lei Yu, Jianli Hao, Wenzhen Chen   +3 more
doaj   +1 more source

Superheater Tube Flat Wall Stationary Temperature Field [PDF]

, 2016
The BKZ-220-100-9 steam generator platen superheater tube flat wall stationary temperature fields analysis have been made. The six steel grades, using in boiler fabrication, namely, St. 10, St. 20, 12H1MF, 15HM, 1H18N9T and 12H18N12T, have been used. The
Loginov, Vladimir Stepanovich, Parpiev, A. T.   +1 more
core   +1 more source

Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility [PDF]

, 2019
CIRCE is a lead–bismuth eutectic alloy (LBE) pool facility aimed to simulate the primary system of a heavy liquid metal (HLM) cooled pool-type fast reactor.
Caruso G., Del Nevo A., Giannetti F., Narcisi V., Tarantino M.   +4 more
core   +1 more source