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HEAT GENERATION
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Thermodynamics Heat Transfer and Fluid Flow Volume 2 of 3
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Flux Profiles

Heat Transfer HEAT GENERATION The fission rate within a nuclear reactor is controlled by several factors.  The density of the fuel, the neutron flux, and the type of fuel all affect the fission rate and, therefore, the heat generation rate.    The  following  equation  is  presented  here  to  show  how  the  heat  generation  rate  (    )  is Q related  to  these  factors.    The  terms  will  be  discussed  in  more  detail  in  the  Nuclear  Science modules. (2-14) Q G  N  sfVf where: = heat generation rate (Btu/sec) Q G     = energy produced per fission (Btu/fission) N     = number of fissionable fuel nuclei/unit volume (atoms/cm3) = microscopic fission cross-section of the fuel (cm2) sf = neutron flux (n/cm2-sec) f Vf    = volume of the fuel (cm3) The thermal power produced by a reactor is directly related to the mass flow rate of the reactor coolant and the temperature difference across the core.   The relationship between power, mass flow rate, and temperature is given in Equation 2-14. (2-15) Q m  cp    DT where: =    heat generation rate (Btu/hr) Q =    mass flow rate (lbm/hr) m cp =    specific heat capacity of reactor coolant system (Btu/lbm-°F) DT   =    temperature difference across core (°F) For  most  types  of  reactors  (boiling  water  reactor  excluded),  the  temperature  of  the  coolant  is dependent upon reactor power and coolant flow rate.   If flow rate is constant, temperature will vary directly with power.   If power is constant, temperature will vary inversely with flow rate. Rev. 0 Page 45 HT-02

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