Background
Most commercial types of nuclear reactor use a pressure vessel to maintain pressure in the reactor plant. This article is a subarticle of Nuclear power. A nuclear reactor is a device in which Nuclear chain reactions are initiated controlled A pressure vessel is a closed container designed to hold gases or liquids at a Pressure different from the ambient Pressure. This is necessary in a pressurized water reactor to prevent boiling in the core, which could lead to a nuclear meltdown. Pressurized water reactor ( PWR s (also VVER if of Russian design are generation II nuclear power reactors that use ordinary Water This is also necessary in other types of reactor plants to prevent moderators from having uncontrolled properties.
Pressure is controlled in a pressurized water reactor to ensure that the core itself does not reach its boiling point in which the water will turn into steam and rapidly decrease the heat being transferred from the fuel to the moderator. Pressurized water reactor ( PWR s (also VVER if of Russian design are generation II nuclear power reactors that use ordinary Water The boiling point of a liquid is the temperature at which the Vapor pressure of the liquid equals the environmental pressure surrounding the liquid By a combination of heaters and spray valves, pressure is controlled in the pressurizer vessel which is connected to the reactor plant. Because the pressurizer vessel and the reactor plant are connected, the pressure of the steam space pressurizes the entire reactor plant to ensure the pressure is above that which would allow boiling in the reactor core. The pressurizer vessel itself may be maintained much hotter than the rest of the reactor plant to ensure pressure control, because in the liquid throughout the reactor plant, pressure applied at any point has an effect on the entire system, whereas the heat transfer is limited by ambient and other losses.
Causes of a loss of pressure control
Many failures in a reactor plant or its supporting auxiliaries could cause a loss of pressure control, including:
- Inadvertent isolation of the pressurizing vessel from the reactor plant, via the closing of an isolation valve or mechanically clogged piping
- A rupture in the pressurizer vessel, which would also be a loss of coolant accident. A loss-of-coolant accident (LOCA is a mode of failure for a Nuclear reactor; if not managed effectively the results of a LOCA could result in reactor core damage In most reactor plant designs, however, this would not limit flowrate through the core and therefore would behave like a loss of pressure control accident rather than a loss of coolant accident.
- Failure of either the spray nozzles (failing open would inhibit raising pressure as the relatively cool spray collapses the pressurizer vessel bubble) or the heaters of the pressurizing system.
- Thermal Stratification of the liquid portion of the pressurizer. When the liquid portion of the pressurizer becomes stratified, the lower layers of water (furthest from the steam bubble) are subcooled and as the steam bubble slowly condenses, pressurizer pressure will appear relatively constant but actually will be slowly lowering. When the operator energizes pressurizer heaters to maintain or raise pressure, pressure will continue to drop until the subcooled water is heated up by the pressurizer heaters to the saturation temperature corresponding to the pressure of the steam (bubble) portion of the pressurizer. During this reheating period, pressure control will be lost, since pressure will still be dropping when it is desired to raise pressure.
Results of a loss of pressure control in a pressurized water reactor
When pressure control is lost in a reactor plant, depending on the level of heat being generated by the reactor plant, the heat being removed by the steam or other auxiliary systems, the initial pressure, and the normal operating temperature of the plant, it could take minutes or even hours for operators to see significant trends in core behaviour.
For whatever power level the reactor is currently operating at, a certain amount of enthalpy is present in the coolant. In Thermodynamics and molecular chemistry, the enthalpy (denoted as H, h, or rarely as χ) is a quotient or description of This enthalpy is proportional to temperature, therefore, the hotter the plant, the higher the pressure must be maintained to prevent boiling. When pressure drops to the saturation point, dryout in the coolant channels will occur.
As the reactor plant heats the water flowing through coolant channels, some of this water becomes steam which is then stripped from the fuel cell walls and into the channel. Normally, these bubbles will collapse in the channel, transferring enthalpy to the surrounding coolant and aiding heat transfer. In Thermodynamics and molecular chemistry, the enthalpy (denoted as H, h, or rarely as χ) is a quotient or description of When the pressure is below the boiling point for the given temperature, sufficient pressure will not be present to collapse the bubble. As more bubbles accumulate in the center of the channel and combine, the steam space within the channel becomes larger and larger until steam blankets the fuel cell walls. Once the fuel cell walls are covered with steam, the rate of heat transfer lowers significantly. This excess heat stays in the fuel cell, potentially causing a nuclear meltdown.
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