Help me about: problem of Thermal Hydraulic

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Discussion Overview

The discussion revolves around solving problems related to Thermal Hydraulic concepts, specifically focusing on calculating the Minimum Critical Power Ratio (MCPR) and pumping power for nuclear reactors. Participants reference specific data and equations from a textbook and seek assistance in understanding and solving these problems.

Discussion Character

  • Homework-related
  • Technical explanation
  • Exploratory

Main Points Raised

  • One participant seeks help with calculating the MCPR and pumping power for a BWR and PWR reactor, respectively, using provided data and equations.
  • Another participant suggests that calculating q'ref for the BWR should be straightforward and questions the significance of Critical Heat Flux (CHF).
  • Participants discuss typical power ratings for BWRs, noting that 10 MWe is not common, and suggest considering Tsat and flow rate in the context of the PWR problem.
  • One participant expresses gratitude for hints received and mentions solving the exercise.
  • Several participants ask for clarification on specific aspects of the problems, such as the location of q'max and additional factors needed to determine pumping power.
  • Another participant proposes a relationship involving volumetric flow rate, pressure drop, and mass flow rate, and inquires about the specific heat capacity (cp) relevant to the calculations.
  • One participant mentions integrating the function along the length of the rod to compute necessary values for the MCPR.
  • There is a discussion about the specific heat of the reactor coolant and the need for an average value or integration based on temperature differences.

Areas of Agreement / Disagreement

Participants express varying levels of understanding and seek clarification on specific calculations, indicating that multiple viewpoints and uncertainties exist regarding the problems presented. No consensus is reached on the solutions.

Contextual Notes

Participants reference specific data from tables and equations, but there are unresolved assumptions regarding the calculations, such as the average temperature for specific heat and the integration process for determining MCPR.

Who May Find This Useful

This discussion may be useful for students or professionals studying Thermal Hydraulic principles, particularly in the context of nuclear engineering and reactor design.

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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