Results 21 to 30 of about 8,242 (166)

Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART

Nuclear Engineering and Technology, 2022
The aim of this research is to analyze the characteristics of a core melt discharged from the reactor vessel and the spreading behavior the core melt in the reactor cavity of the SMART.
Sang Ho Kim, Jaehyun Ham, Byeonghee Lee, Sung Il Kim, Hwan Yeol Kim, Rae-Joon Park, Jaehoon Jung   +6 more
doaj   +1 more source

Effect of Tank Diameter on Solid Suspension in Industrial Reactor Vessels [PDF]

Journal of Applied Fluid Mechanics
Present research study analyses the suitability of baffled reactor vessels with large diameter agitated using the Rushton Turbine (RT) impeller maintained at standard clearance condition for the solid-liquid suspension process.
D. K. Iyer, A. K. Patel
doaj   +1 more source

Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels

Mathematics, 2022
The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels.
Alvaro Rodríguez-Prieto, Manuel Callejas, Ernesto Primera, Guglielmo Lomonaco, Ana María Camacho   +4 more
doaj   +1 more source

Research Progress of Steels for Nuclear Reactor Pressure Vessels

Materials, 2022
The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance requirements for nuclear pressure vessel steel.
Zhou, Linjun, Dai, Jie, Li, Yang, Dai, Xin, Xie, Changsheng, Li, Linze, Chen, Liansheng   +6 more
openaire   +2 more sources

A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

Energies, 2022
The operation of many nuclear pressurized water reactors is being extended beyond their design lifetime limit. From the perspective of possible further lifetime extension, safety requirements are a priority.
Romain Vuiart, Mariya Brovchenko, Julien Taforeau, Eric Dumonteil   +3 more
doaj   +1 more source

CFD analysis of coolant flow in the nuclear reactor VVER440 [PDF]

Applied and Computational Mechanics, 2007
The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the reactor pressure vessel (RPV) outlet and under the RPV head.
Katolický J., Bláha M., Frelich J., Jícha M.   +3 more
doaj  

Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor

Science and Technology of Nuclear Installations, 2018
One of the severe accident management strategies for nuclear reactors is the melted corium retention inside the reactor pressure vessel. The work presented in this article investigates the application of in-vessel retention (IVR) severe accident ...
Mindaugas Valinčius, Tadas Kaliatka, Algirdas Kaliatka, Eugenijus Ušpuras   +3 more
doaj   +1 more source

Periodic Inspection Program of Nuclear PWR reactor Pressure Vessel

Brazilian Journal of Radiation Sciences, 2021
This work aims to present a methodology that guides the operating organization to carry out periodic inspections in the nuclear PWR reactor pressure vessels. At first, fundamental concepts of nuclear energy and their application were discussed.
Anne Aguiar Araujo
doaj   +1 more source

Model Materials for Reactor Pressure Vessel

Acta Physica Polonica A, 2010
In this paper we report preliminary results from a study focused on investigation of the role of elements as Cr, Ni, Mn and Si in the radiation stability of reactor pressure vessel steels. Twelve model ferritic steels and eight model welds with basic composition derived from Russian VVER-1000 and Western PWR reactor pressure vessel materials were ...
J. Degmová, L. Debarberis, V. Kršjak
openaire   +1 more source

Transient heat transfer and crust evolution during debris bed melting process in the hypothetical severe accident of HPR1000

Nuclear Engineering and Technology, 2023
In the late in-vessel phase of a nuclear reactor severe accident, the internal heat transfer and crust evolution during the debris bed melting process have important effects on the thermal load distribution along the vessel wall, and further affect the ...
Chao Lv, Gen Li, Jinchen Gao, Jinshi Wang, Junjie Yan   +4 more
doaj   +1 more source