A Pressurized Water Reactor is fueled with $4\mathrm{.}25\%$ enriched $U{O}_2$ fuel. For an effective fission cross section of $350$ barns and an average neutron flux in the core of $1\mathrm{.}5{10}^{13}$ neutrons per second per square centimeter, determine the volumetric heat generation rate of the fuel in $\frac{W}{c}{m}^3.$ Assume a $U{O}_2$ density of $10\mathrm{.}5g\frac{m}{c}{m}^3$ and that each fission deposits $190$MeV in the fuel.