Vertical steam generators tube bundles vibrations
MORSKIE INTELLEKTUAL`NYE TEHNOLOGII)</msg>, 2020 Представлена реализация расчетного метода для определения и анализа параметров вибрации трубных пучков парогенераторов (ПГ), обтекаемых поперечным турбулентным потоком жидкого теплоносителя. В связи с известными случаями выхода из строя энергетического оборудования вследствие истирания труб ПГ в дистанционирующих решетках, решение данной задачи весьма ...
openaire +1 more source
Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident. [PDF]
Materials (Basel), 2021 Wang DS +7 more
europepmc +1 more source
Failure prediction method of heat transfer tube of nuclear power steam generator based on WOA-SVR
Journal of Radiation Research and Applied SciencesSteam generator is the key equipment for energy conversion in nuclear power plants. The high temperature and high pressure fluid flowing inside the steam generator will cause flow-induced vibration of heat transfer tubes, resulting in fretting wear ...
Xianwei Wu +5 more
doaj +1 more source
Pressure Waves due to Rapid Evaporation of Water Droplet in Liquid Lead Coolant
Science and Technology of Nuclear Installations, 2018 Flash evaporation of a superheated water droplet in heavy liquid metal coolant (lead) is considered, in application to the analysis of a lead-cooled fast reactor steam generator tube rupture accident.
S. E. Yakush +3 more
doaj +1 more source
Sensors, 2018 In order to access the fretting damage of the steam generator tube (SGT), a fast fiber Fabry-Perot (F-P) non-scanning correlation demodulation system based on a super luminescent light emitting diode (SLED) was performed. By demodulating the light signal
Peijian Huang +5 more
doaj +1 more source
Assessment of Choking Flow Models in RELAP5 for Subcooled Choking Flow Through a Small Axial Crack of a Steam Generator Tube [PDF]
, 2017 Choking flow plays an integral part not only in the engineered safeguards of a nuclear power plant (NPP), but also to everyday operation. Current NPP steam generators operate on the leak-before-break approach.
Jovica Riznic +3 more
core +1 more source
Investigation of a Steam Generator Tube Rupture Sequence Using VICTORIA [PDF]
, 1995 VICTORIA-92 is a mechanistic computer code for analyzing fission product behavior within the reactor coolant system (RCS) during a severe reactor accident. It provides detailed predictions of the release of radionuclides and nonradioactive materials from
Erickson, C. M. +2 more
core
Key Findings from the Artist Project on Aerosol Retention in a Dry Steam Generator
Nuclear Engineering and Technology, 2016 A steam generator tube rupture (SGTR) event with a stuck-open safety relief valve constitutes one of the most serious accident sequences in pressurized water reactors (PWRs) because it may create an open path for radioactive aerosol release into the ...
Abdelouahab Dehbi +5 more
doaj +1 more source
Steam-generator-tube-rupture transients for pressurized-water reactors [PDF]
, 1982 Steam generator tube ruptures with and without concurrent main-steam-line break are investigated for pressurized water reactors supplied by the major US vendors.
Dobranich, D. +2 more
core
Steam generator tube integrity program: Phase II, Final report [PDF]
, 1988 The Steam Generator Tube Integrity Program (SGTIP) was a three phase program conducted for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL).
Wheeler, K. R. +5 more
core +1 more source