Exceeding the saturation temperature of coolant on the clad for PWR

In summary, the conversation discusses the possibility of cladding temperature exceeding the saturation temperature of coolant in a PWR reactor, potentially leading to boiling in certain zones. It is permissible to have nucleate boiling in a PWR core, but it is generally avoided to prevent damage to the fuel and cladding. Different correlations can be used to calculate the wall temperature that would produce nucleate boiling.
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nuclearsneke
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TL;DR Summary
tl;dr: is it likely for cladding temperautre to exceed the coolant saturation temperature in PWR reactor?
Hello there.

I have been conducting a thermal calculation of a fuel assembly for KLT-40S reactor (a small modular PWR-like reactor installed at the floating nuclear power plant "Akademik Lomonosov" with electric power of 35 MWe.) and obtained some interesting results. It seems that cladding temperature exceeds the saturation temperature of coolant by 30-60 degrees and it happens mostly in the center of the fuel rod's height.
I believe it could lead to boiling of coolant in these zones. But questions is: is it allowable for PWR reactor core to have some axial zones with boiling? And am I right about this case of boiling?

If you provided to your point of view some sources to refference at, it would be also a great piece of help. Thanks in advance.
 
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nuclearsneke said:
Summary: tl;dr: is it likely for cladding temperautre to exceed the coolant saturation temperature in PWR reactor?

But questions is: is it allowable for PWR reactor core to have some axial zones with boiling? And am I right about this case of boiling?
It is permissible to have nucleate boiling in a PWR core, and some German plants have done so routinely. Some US plants may have some nucleate boiling, probably on the order of a few percent, and in the upper spans of the core. However, in general, to preclude high oxide thicknesses, most PWRs try to avoid nucleate boiling.

Edit/update - Departure from Nucleate Boiling (DNB) is strongly discouraged. DNB would damage the fuel, or otherwise, weaken the cladding.
 
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There is some nucleate boiling (also called subcooled boiling) in most (if not all) PWR reactors. There isn't a lot, but it is present.

Having a wall temperature greater than the saturation temperature does not guarantee you will have nucleate boiling. The wall temperature has to be greater than the saturation temperature by some amount.

There are several correlations that can be used to calculate the wall temperature (Twall) that will produce nucleate boiling. These correlations include Jens-Lotte, Thom, and Chen. I did a quick search and came up with this webpage that shows the Thom and Chen correlations:

https://www.thermal-engineering.org/what-is-nucleate-boiling-definition/

Note that the different correlations will give different results, and sometimes the differences are significant. I suggest looking in multiple textbooks and making sure the correlations are valid over the pressure ranges you will be applying them.
 
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FAQ: Exceeding the saturation temperature of coolant on the clad for PWR

What is the saturation temperature of coolant on the clad for PWR?

The saturation temperature of coolant on the clad for PWR refers to the temperature at which the coolant reaches its boiling point and begins to vaporize. This typically occurs at around 300-320 degrees Celsius for pressurized water reactors (PWRs).

What happens if the coolant exceeds the saturation temperature on the clad for PWR?

If the coolant exceeds the saturation temperature on the clad for PWR, it can lead to the formation of steam bubbles within the coolant. This can cause a phenomenon known as "film boiling" where a layer of steam forms on the surface of the clad, reducing its ability to transfer heat and potentially leading to overheating and damage.

How is the saturation temperature of coolant on the clad for PWR controlled?

The saturation temperature of coolant on the clad for PWR is controlled through the use of a pressurizer. This device maintains the pressure within the reactor vessel, which in turn affects the boiling point of the coolant. By adjusting the pressure, the saturation temperature can be kept within safe limits.

What are the potential consequences of exceeding the saturation temperature on the clad for PWR?

If the saturation temperature on the clad for PWR is exceeded, it can lead to a loss of coolant accident (LOCA) where the reactor core is no longer properly cooled. This can result in the release of radioactive materials and potentially lead to a meltdown of the nuclear fuel rods.

How is the saturation temperature of coolant on the clad for PWR monitored?

The saturation temperature of coolant on the clad for PWR is continuously monitored by sensors within the reactor vessel. These sensors measure the temperature and pressure of the coolant and provide feedback to the control system, which can then adjust the pressurizer as needed to maintain safe conditions.

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