Help me about: problem of Thermal Hydraulic

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SUMMARY

This discussion focuses on the calculation of the Minimum Critical Power Ratio (MCPR) and pumping power in Thermal Hydraulic systems, specifically for a 10 MWe Boiling Water Reactor (BWR) and a Pressurized Water Reactor (PWR). Key formulas include the axial linear power shape, q'(z) = q'ref*exp(-az/L)sin(pi*z/L), with a critical bundle power of 93 19kW. Participants emphasize the importance of understanding the relationship between flow rate, pressure drop, and specific heat (Cp) of the reactor coolant, particularly in the context of steady-state operating conditions.

PREREQUISITES
  • Understanding of Thermal Hydraulic principles
  • Familiarity with reactor types, specifically BWR and PWR
  • Knowledge of critical power ratios and their significance
  • Ability to perform calculations involving heat transfer and fluid dynamics
NEXT STEPS
  • Study the calculation methods for Minimum Critical Power Ratio (MCPR) in detail
  • Research the specific heat (Cp) of water and its application in reactor coolant systems
  • Learn about pressure drop calculations in thermal hydraulic loops
  • Explore the axial linear power distribution in nuclear reactors
USEFUL FOR

Nuclear engineering students, thermal hydraulic engineers, and professionals involved in reactor design and safety analysis will benefit from this discussion.

marlh
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I'm studying about Thermal Hydraulic. When i read book :"NUCLEAR SYSTEMS I Thermal Hydraulic Fundamentals" - Neil E. Todreas and Mujid S. Kazimi.

I don't understand about : calculate "Minimum critical power ratio" & calculate "Pumping power" in problem:

a) Calculate the minimum critical power ratio for a typical 10 MWe BWR operating at 100% power using the data in Tables 1-2, 1-3, and 2-3 . Assume that:

1. The axial linear power shape can be expressed as

q'(z) = q'ref*exp (- az/L )sin (pi*z/L)
where a = 1.96. Determine q'ref such that qmax = 44 kW/m
2. The critical bundle power is 93 19kW.b) Calculate the pumping power under steady-state operating conditions for a typical PWR reactor coolant system. Assume the following operating conditions:
Core power = 38 17 MWt
detal Tcore = 31 °C
Reactor coolant system pressure drop = 778 kPa (1 13 psi)

can anyone help me solve the problem ? or guide me solve the problem. thank!
 
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For a, that should be straightforward to calculate q'ref. Find the elevation for qmax. BWRs are not typically 10 MWe, but more like 1 GWe (1000 MWe), and actually > 1 GWe.

What is the significant of CHF?


For b, that's not really typical - 3817 MWt would be typical of the Palo Verde units. Think about Tsat as a possible constraint, and the flow rate of coolant to get a ΔT = 31°C at a power (rate of enthalpy input) of 3817 MWt. Relate flow rate to the pressure drop around the loop. Likely the plant would have 4 loops, or 2 hot legs and 4 cold legs.
 
Thank for Astronuc about hint. I have solved the exercise.:smile:
 
actually i have same question for these two problem, can you help me with it, i couldn't find it through the hints given
 
matt222 said:
actually i have same question for these two problem, can you help me with it, i couldn't find it through the hints given
Given q'(z), at what location does one find q'max.

For pumping power, besides the pressure drop, what does one need in order to determine the power (rate of work) to pump the coolant around the loop? Relate flow rate to the pressure drop around the loop.
 
we can say that, p=volumetric flow rate*pressure drop
volumetric flow rate =mass flow rate/density of water
mass flow rate=(cp*delta T)/power

is it true and what is the cp in this case?
 
for first part i found the location but how about finding minimum critical power ratio MCPR
 
LOL!

You are either in my class or nuclear engineering curriculims throughout the US follows a set curriculim

for a

once you solved for qref just intergrate the function along the length of the rod so you have both numbers needed to compute the ratio.

haven't finished part b due friday got some time. I would assume the Cp of water since this is a PWR
 
matt222 said:
is it true and what is the cp in this case?
This would be the specific heat of the reactor coolant. You will need to find a suitable average value for the temperature difference or integrate if your professor requires (like mine did many years ago).

Interesting to see they are still using Todreas - used this book in graduate school in 1991.
 

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