Induced nuclear reactions: processes – systems – and elements – With control of reactor – By movement of control element or by release of neutron...
Reexamination Certificate
2002-04-12
2004-10-12
Behrend, Harvey E. (Department: 3641)
Induced nuclear reactions: processes, systems, and elements
With control of reactor
By movement of control element or by release of neutron...
C376S231000, C376S336000, C376S381000
Reexamination Certificate
active
06804320
ABSTRACT:
FIELD OF THE INVENTION
The invention generally pertains to nuclear reactor systems, and more specifically, to automatically scramming nuclear reactor systems.
BACKGROUND OF THE INVENTION
There are over four-hundred nuclear power plants worldwide, providing nearly twenty percent of the world's electricity. Nuclear power plants function much like power-generating plants that are fueled by coal or oil. That is, either type of power plant generates heat. The heat is used to heat water and produce steam, or to heat a gas. The steam or the gas, as the case may be, drives one or more turbines which in turn generate electricity. The difference, of course, is that heat is generated at a nuclear power plant by nuclear reactions (i.e., induced fission) instead of by burning coal or oil.
Induced fission takes place in the reactor. The fuel for the reactor is provided by a suitable radioactive material (e.g., uranium-235 or plutonium-239) typically formed into either rods or “pebbles” that are arranged within the core of the reactor. As the fuel fissions, neutrons are released which bombard the nuclei of the other fuel atoms in the core of the reactor. The bombarded nuclei absorb the neutrons causing the nuclei to become unstable and split, releasing one or more neutrons which bombard the nuclei of yet other fuel atoms, and so on. The split atoms release energy in the form of radiation and heat.
During operation of the reactor, a coolant is passed through the core of the reactor to maintain the reactor at a normal operating temperature and keep it from overheating. The coolant may be either a gas-phase coolant (e.g., helium) or a liquid-phase coolant (e.g., water) that flows into the reactor, absorbs the heat produced during induced fission, and flows out of the reactor.
The heated coolant that flows out of the reactor may then be passed through a heat-exchanger. Water is also provided to the heat exchanger to absorb heat from the heated coolant. The coolant is then recirculated into the reactor. The heat absorbed by the water produces steam. This steam is used to drive the turbines that operate the generator and generate electricity. Alternatively, in a direct cycle gas-cooled reactor the cooling fluid is used directly to drive the turbines.
In some circumstances, the flow of coolant into the reactor may be insufficient to cool the reactor. As an example, the flow of coolant into the reactor may be interrupted by a blockage in the pipe system or failure of a pump, reducing or altogether stopping the flow of coolant into the reactor. When this happens, the reactor must be shut down so that the reactor does not overheat.
The reactor is provided with one or more control elements that can be lowered into the reactor to slow and eventually stop the reactions occurring therein when the reactor exceeds a safe operating temperature. Control elements may be made from a variety of materials that absorb free neutrons. When the control elements are lowered into the reactor, the control elements absorb the neutrons instead of the neutrons being absorbed by the fuel, causing the reactor to shut down.
Typically, a number of monitors are used to determine how much heat is being generated in the reactor. For example, the monitors may measure the temperature in the reactor. When the temperature in the reactor exceeds safe operating conditions, the monitors signal an emergency response system which in turn lowers the control elements into the reactor to shut it down. For safety reasons redundant monitors are commonly provided so that if one fails, another of the monitors will still signal the emergency response system of the unsafe operating condition so that it can shut down the reactor. However, the monitors must still signal the emergency response system when the unsafe condition occurs, thereby introducing delay and another potential point of failure. In addition, such redundant monitors can be complex and therefore expensive.
SUMMARY OF THE INVENTION
An embodiment of an automatically scramming nuclear reactor system of the present invention may comprise 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 of the core and removes heated coolant from the coolant outlet end of the core. The flow of coolant through the reactor maintains a pressure differential between the coolant inlet end of the core and the coolant outlet end of the core during a normal operating condition of the nuclear reactor system. A guide tube having a first end and a second end is positioned within the core. The first end of the guide tube is in fluid communication with the coolant inlet end of the core, and the second end of the guide tube is in fluid communication with the coolant outlet end of the core. A control element is positioned within the guide tube and is movable within the guide tube between an upper position and a lower position. The control element automatically falls under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.
A method for scramming a nuclear reactor system is also disclosed and may comprise the steps of providing a coolant to a core of the nuclear reactor system at a first pressure, removing heated coolant from the core of the nuclear reactor system at a second pressure, the first pressure being greater than the second pressure during a normal operating condition of the nuclear reactor system, using a pressure differential between the first and second pressures to hold a control element above a scramming position during the normal operating condition of the nuclear reactor system, and the control element automatically falling under the action of gravity to the scramming position when the pressure differential drops below a safe pressure differential.
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Fluidization and Fluid—Particle Systems, Zenz et al (editors), Reinhold Pub. Corp. New York, pp 41-44 1960.
Ougouag Abderrafi M.
Schultz Richard R.
Terry William K.
Bechtel BWXT Idaho LLC
Behrend Harvey E.
Dahl & Osterloth LLP
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