By Jess C Gehin
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Additional resources for A quasi-static polynomial nodal method for nuclear reactor analysis
Arl)ilrary, timeoindependent We Call now substitute (',;,17) the factorizntio. bt;ti. wtV l_,. Mplt) .... _ ,X,/wTc_lt) t w'rqlt), 5! i. f the followin! fnct "r(t) _. lt of this the time derivative term can t)e written an wry 'sit)'rit = .... ;ii The alttpiitude function equKtion i_ then obtained ' , l! d by dividing by wl"M(t )S(t )where M(ti in tile totJtl It'nnmtt* ,q)eratc,r di! ctio, - i. "'_ w rM(t)Sit ) wr q(t) _ .... M(t) L(t)! S(t) pitt ..... 24c i ate the reactivity, effective delayed neutron fractions and prompt neutron life time, respectively.
Lllll I IP u_ i l ....... IJJL i Compute the Discontinuity Factor R_tios using the Polynond_d Currents and the Finite. Difference Fluxes _t_.. averaged fluxes converge. The uniqueness that, if this tnethod of the solution of the nodal equations guarantees converges, it will converge to the solution of the polynomial nodal equations. difference calculation. difference equations involve only tile nodal fluxes, no iterations are necessary for the currents and expansion coefficients during the global flux solution procedure.
At initial flow rate (erg/s cm 2 K) initial total coolant mass flow rate (g/s) total coolant mass flow rate (g/s) coolant mass flow rate in node (i,j,k)(g/s) = energy required to raise the temperature of a unit volume of coolant one temperature unit (erg/cm 3 K). mplementations. 34b) are set to zero. Transient applications 57 to maintain consistency with earlier the time derivatives in Eqs. phase L flow models are included. , Cross Section Feedback For the purposes of this investigation, hydraulics behavior the cross section feedback from the thermal.