6.4 Calculate the energy yield from the following fission reactions (a) ^235_92U + ^1_0n ? ^92_37Rb + ^140_55Cs + 4 ^1_0n + Q (b) ^235_92U + ^1_0n ? ^94_38Sr + ^140_54Xe + 2 ^1_0n + Q (c) ^235_92U + ^1_0n ? ^92_36Kr + ^141_56Ba + 3 ^1_0n + Q (d) ^233_92U + ^1_0n ? ^94_38Sr + ^137_54Xe + 3 ^1_0n + Q (e) ^239_94Pu + ^1_0n ? ^103_40Zr + ^134_54Xe + 3 ^1_0n + Q
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