Exceeding the saturation temperature of coolant on the clad for PWR

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SUMMARY

The discussion centers on the thermal calculations of a fuel assembly for the KLT-40S reactor, where cladding temperatures exceed the saturation temperature of coolant by 30-60 degrees Celsius, particularly at the center of the fuel rod's height. It is established that nucleate boiling is permissible in PWR reactor cores, with some German and US plants experiencing it to varying degrees. However, Departure from Nucleate Boiling (DNB) is strongly discouraged due to potential damage to fuel and cladding. Various correlations, including Jens-Lotte, Thom, and Chen, can be utilized to calculate the wall temperature necessary for nucleate boiling.

PREREQUISITES
  • Understanding of PWR reactor thermal dynamics
  • Familiarity with nucleate boiling concepts
  • Knowledge of thermal correlations such as Jens-Lotte, Thom, and Chen
  • Basic principles of fuel assembly design in nuclear reactors
NEXT STEPS
  • Research the Jens-Lotte correlation for nucleate boiling calculations
  • Study the Thom correlation and its applications in thermal engineering
  • Examine the implications of Departure from Nucleate Boiling (DNB) in PWR reactors
  • Explore thermal management strategies in small modular reactors like KLT-40S
USEFUL FOR

Nuclear engineers, thermal analysts, and professionals involved in the design and operation of PWR reactors will benefit from this discussion, particularly those focused on fuel assembly performance and coolant dynamics.

nuclearsneke
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TL;DR
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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