List the 3 source terms and 2 loss terms for Pu-239 for a flux of 0.5x10^24 neutrons/cm^2 sec. Label the nuclide number densities and give the numerical values of the multipliers. dt dn(t) = n^-1 0 1 - 1 0 + no n'o + + n'x' - no+ - n no n all j all i 15 238 239 U 240U 2.7 22 23.5 min 14.1 h 2100 2100 238 NP 2.12 d 239 Np 240 NP 60. 2.35 d 7.2 min 62 min 200 1010 750 78 238 pu 239Pu 271 240 Pu 290 241 pu Pu 361 242 pu 19 243pu 90 4.96 h 540 14.4 y 243 8 Am 241 78 Am 600 -DECA