Method for automatically scramming a nuclear reactor
View Patent ↗An automatically scramming nuclear reactor system. One embodiment comprises a core having a coolant inlet end and a coolant outlet end. A cooling system operatively associated with the core provides coolant to the coolant inlet end and removes heated coolant from the coolant outlet end, thus maintaining a pressure differential therebetween during a normal operating condition of the nuclear reactor system. A guide tube is positioned within the core with a first end of the guide tube in fluid communication with the coolant inlet end of the core, and a second end of the guide tube in fluid communication with the coolant outlet end of the core. A control element is positioned within the guide tube and is movable therein between upper and lower positions, and automatically falls under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.
1. A method for scramming a nuclear reactor system, comprising:
positioning a guide tube within a core of said nuclear reactor, said guide tube comprising:
an elongated inlet section having a proximal end and a distal end, the proximal end of the inlet section defining a first end of the guide tube, the first end of the guide tube being in fluid communication with a coolant inlet end of the core;
a substantially straight control element section extending generally upwardly through the core, the control element section having a proximal end and a distal end;
a first U-shaped section fluidically connecting the distal end of the inlet section and the proximal end of the control element section;
an elongated outlet section having a proximal end and a distal end, the distal end of the outlet section defining a second end of the guide tube, the second end of said guide tube being in fluid communication with a coolant outlet end of the core, the coolant outlet end of the core being located at a position below the coolant inlet end of the core; and
a second U-shaped section fluidically connecting the distal end of the control element section and the proximal end of the outlet section;
positioning a control element within the control element section of the guide tube, the control element being moveable within the control element section of the guide tube between an upper position and a lower position;
providing a coolant to the coolant inlet end of the core;
removing heated coolant from the coolant outlet end of the core, said providing coolant and said removing heated coolant creating a pressure differential across the control element section of the guide tube; and
using the pressure differential to hold the control element at about the upper position in the control element section of the guide tube, the control element automatically falling under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.
2. The method of claim 1 , wherein using the pressure differential to hold the control element at about the upper position comprises using primarily a static pressure component of the pressure differential to hold the control element at about the upper position.
3. The method of claim 1 , wherein using the lift force to hold a control element above a scramming position comprises using primarily a dynamic pressure component of a bypass flow of coolant to hold the control element above the scramming position.
4. The method of claim 1 , wherein said step of providing a coolant comprises providing a coolant in a gas phase.