![]() The main difference between MOX fuels from uranium fuel is that MOX fuel contains more fissile material than uranium fuel. MOX fuel is a mixture of plutonium oxide (from spent fuel) and uranium oxide (natural uranium), with about 3 to 5 percent by weight of plutonium. In this paper, the decay heat of thermal-induced fission of MOX fuel averaged over 100 fissions of its fissile nuclei (U235, Pu239, and Pu241) was calculated. In this case, a specially developed program that can work with large data sets can be used to solve huge numbers of differential equations of type initial value problems in less time, for example, MATLAB software, MATHCAD, which have a number of built-in tools that make it easier to work with, access, and manipulate a large number of initial value problems differential equations. ![]() In this paper, the second method, which depends on solving Bateman’s equation numerically, was used to model the decay of fission fragments. Table 1 shows some of the programs and codes that have been used to solve problems related to the calculation of fission products inventory and decay heat released due to fission fragments. Most of these calculations are done depending on two methods exclusively for finding the inventory of fission products, either simulating statistically decomposing all fission fragments by tracking each event individually or solving the Batman equation. Modeling the inventory of fission products after the fission burst of different fissionable nuclei as well as calculating the decay heat released due to the decay of these fission fragments has been presented in several kinds of literature. Moreover, the code showed high capability in calculating the fission fragments inventories and decay heats due to the decay of fission fragments of 31 fissionable nuclei. Calculations of decay heat show very common trends for a period of 10 7 sec after the fission burst of thermal fissions of individual fissile nuclei. The method used has been validated by several comparisons before, but the new in this work is using the most recent Evaluated Nuclear Data Library ENDF/B-VIII.0. ![]() The most influential nuclei in the decay heat were also identified. The average decay heat of the MOX fuel in induced thermal fission is also concluded. The decay heat calculations for the three fissile materials are directly calculated using the summation method by knowing the different concentrations of fission products over time. A numerical method was used in this work to calculate the concentrations of all fission products due to the individual thermal fission of the three fissile materials as a function of time N( t). Decay heat calculation of the weighted fissile material content in MOX fuel is also important. These fissile nuclei are the main source of the decay heat in MOX fuel. It is important to calculate the nuclear decay heat due to the single thermal fission (fission due to 0.0235 eV neutron) for all fissile nuclei in the MOX fuels (U 235, Pu 239, and Pu 241). MIXED Oxide Nuclear fuel (MOX) contains both uranium and plutonium in oxidized form.
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