scholarly journals Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions

2017 ◽  
Vol 67 (1) ◽  
pp. 87-92
Author(s):  
Juraj Paulech ◽  
Vladimír Kutiš ◽  
Gabriel Gálik ◽  
Jakub Jakubec ◽  
Tibor Sedlár
Keyword(s):  
Numerical Simulation ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Reactor Pressure Vessel ◽  
Spent Fuel ◽  
Storage Pool ◽  
Hydraulic Behaviour ◽  
Fuel Storage ◽  
Heating Up ◽  
Reactor Pressure

Abstract The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in the VVER- 440 nuclear reactor under standard outage conditions. Heating-up and flow of coolant between the reactor pressure vessel and spent fuel storage pool are discussed.

NERO: A Teleoperated Wall Climbing Vehicle for Assisting Inspection of a Nuclear Reactor Pressure Vessel

1993 ◽  
Author(s):  
B. L. Luk ◽  
A. A. Collie ◽  
T. White
Keyword(s):  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Vertical Surface ◽  
Reactor Pressure Vessel ◽  
Control Console ◽  
The Status ◽  
Walking Mechanism ◽  
Reactor Pressure

Abstract NERO is a series of teleoperated wall climbing vehicles. Each vehicle carries a specific tool for assisting inspection of a nuclear reactor pressure vessel in the U.K. They adopted a simple sliding frame walking mechanism to cope with 250mm head room and 25mm obstacles on the surface. Vacuum suckers are used by the vehicle for climbing vertical surface. The NERO vehicle is driven remotely by an operator via a control console. The status of the vehicle and the control console is displayed on the console’s computer monitor. These vehicles completed their tasks successfully by September 1992.

Role of Residual Stresses and Strains Fields Generated by Heat Treatments on the Hydrogen Embrittlement of a Nuclear Reactor Pressure Vessel

2011 ◽  
Author(s):  
J. Toribio ◽  
D. Vergara ◽  
M. Lorenzo ◽  
J. J. Marti´n
Keyword(s):  
Hydrogen Embrittlement ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Hydrogen Diffusion ◽  
Operation Time ◽  
Heat Treatments ◽  
Reactor Pressure Vessel ◽  
Low Carbon ◽  
Tempering Temperature ◽  
Reactor Pressure

The wall of a nuclear reactor pressure vessel can undergo a reduction of its mechanical properties due to the presence of hydrogen, a process known as hydrogen embrittlement (HE). A numerical model of hydrogen diffusion assisted by stress and strain was used in this paper to evaluate the HE process in the wall of a real nuclear reactor pressure vessel, formed by a bimaterial (stainless steel and low carbon steel). In this sense, a quantitative analysis was carried out of the influence of tempering heat treatments conditions applied to these two steels on hydrogen concentration accumulated in the nuclear reactor vessel during its operation time. To this end, the most relevant parameters of these heat treatments were considered: (i) tempering temperature and (ii) tempering time.

Sign in / Sign up

Export Citation Format

Share Document