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A Common Induced Fission Process in a Thermal Nuclear Reactor

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A common induced fission process in a thermal nuclear reactor is n+235U236U137Xe+97Sr+xn\mathrm { n } + { } ^ { 235 } \mathrm { U } \rightarrow { } ^ { 236 } \mathrm { U } \rightarrow { } ^ { 137 } \mathrm { Xe } + { } ^ { 97 } \mathrm { Sr } + x \mathrm { n } (a) Determine the number of neutrons, xx , on the right hand side of the equation.
(b) Calculate the fission energy associated with this process. Note: m(137Xe)=m \left( { } ^ { 137 } \mathrm { Xe } \right) = 136.9115629u;m(97Sr)=96.926153u136.9115629 \mathrm { u } ; m \left( { } ^ { 97 } \mathrm { Sr } \right) = 96.926153 \mathrm { u } .


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