Results 31 to 40 of about 8,242 (166)
Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident
Science and Technology of Nuclear Installations, 2012 The objective of this paper is the simulation and analysis of the BoilingWater Reactor (BWR) lower head during a severe accident. The COUPLE computer code was used in this work to model the heatup of the reactor core material that slumps in the lower ...
Alejandro Nuñez-Carrera +3 more
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Weibull stress analysis for the corner crack in reactor pressure vessel nozzle
Advances in Mechanical Engineering, 2019 The nozzle region of a reactor pressure vessel experiences higher and more complex stresses than the remaining part of the reactor pressure vessel. If a corner crack is postulated in the nozzle region, it is necessary to consider the potential strong ...
Ting Jin +5 more
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Reactor pressure vessel. Status report [PDF]
, 1996 This report describes the issues raised as a result of the staffs review of Generic Letter (GL) 92-01, Revision 1, responses and plant-specific reactor pressure vessel (RPV) assessments and the actions taken or work in progress to address these issues.
Elliot, B. J. +2 more
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FluidsThis article presents an experimental study on the hydrodynamics of coolant flow within the pressure vessel of a small modular reactor (SMR) cooled with water, including areas such as the annular downcomer, bottom chamber, and core-simulating channels ...
Anton Riazanov +8 more
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Estimation of the error of functionals calculation results of the neutron flux onto the WWER 1000 reactor pressure vessel [PDF]
Ядерна фізика та енергетика, 2012 It is shown that systematic calculation errors of functionals of the neutron flux onto WWER 1000 reactor pressure vessel are pseudorandom. The error of the neutron flux functionals is estimated on the basis of this fact and the data obtained with the ...
V. L. Diemokhin +2 more
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EPJ Web of Conferences, 2016 The 2D/1D synthesis methodology has been used to calculate the fast neutron (E > 1.0 MeV) exposure to the beltline region of the reactor pressure vessel.
Lim Mi Joung +3 more
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Nuclear Engineering and Technology, 2013 MAAP4 is a computer code that can simulate the response of a light water reactor power plant during severe accident sequences, including actions taken as part of accident management.
KEVIN ROBERTS, ROBERT SANDERS
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Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions
Journal of Mechanical Engineering, 2017 The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in the VVER- 440 nuclear reactor under standard outage conditions.
Paulech Juraj +4 more
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Nuclear Engineering and TechnologyMolten corium may be discharged into the reactor cavity if the Reactor Pressure Vessel (RPV) fails during a severe accident. The cooling and stabilization of the discharged molten corium in the reactor cavity are crucial for preventing further accident ...
Jaehoon Jung, Seokgyu Jeong
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Physical principles of the nuclear burning wave reactor. I [PDF]
Ядерна фізика та енергетика, 2008 Results to support reliability of the VVER ex-vessel dosimetry neutron-activation detector spectrometric data are presented. It is shown. that detector specific activity values can be used for validation of the reactor pressure vessel radiation exposure ...
V. N. Bukanov +3 more
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