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Problem from Nuclear System I - Thermal Hydraulics Fundamentals

12/04/2011 1:44 AM

Problem 7-4 Loss of heat sink in a sodium-cooled reactor (section II)A 1000 MW(t) sodium-cooled fast reactor has three identical coolant loops. The reactor vessel is tilled with sodium to a prescribed level, with the remainder of the vessel being occupied by an inert cover gas, as shown in Figure 7-26 . Under the steady operating condition, the ratio of the volume of cover gas to that of sodium in the primary system is 0. 1. At time t = 0, the primary system of this reactor suffers a complete loss of heat sink accident, and the reactor power instantly drops to 2% of full power. Using a lumped parameter approach, calculate the pressure of the primary system at time t = 60 seconds. At this time, check if the sodium is boiling.Useful dataInitial average primary system temperature = 980°FInitial primary system pressure = 50 psiTotal primary system coolant mass = 18,000 Ibmβ (volumetric coefficient of thermal expansion of sodium)= 1 .6( 10 ^- 4) ; oFcp for sodium = 0.3 BTU/Ibm OF (at 980°F)ρ for sodium = 51.4 lbm/ft) (at 980°F)Sodium saturated vapor pressure:p = exp [18.832 - (13113/ T) - 1.0948 ln T + 1.9777 (10^(-4)) T]where p is in atmospheres and T is in OK.
Answer: p = 87.9 psiT = 1190.7°F, so no boiling occurs
can anybody solve this question this is taken from chapter-7 of Nuclear system I- Thermal Hydraulics Fundamentals

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Guru

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#1

Re: Problem from Nuclear system I- Thermal Hydraulics Fundamentals

12/04/2011 2:21 AM

Do your own homework.

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Guru
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#2

Re: Problem from Nuclear system I- Thermal Hydraulics Fundamentals

12/04/2011 2:11 PM

Have you tried re-creating the problem as a real world experiment?

Optionally re-read the text book (and associated text books) or ask your lecturer. All the information you need should be in there.

Jack - Nuclear Free down here.

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Guru
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#3

Re: Problem from Nuclear System I - Thermal Hydraulics Fundamentals

12/06/2011 3:08 AM

"Shields up! Evasive manoeuvres, Mr. Sulu!"

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