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Evaluation of Depletion and Production of Uranium, Plutonium, Transplutonium Nuclides, and Fission Products in JPDR-1 Fuel

Hideo Ezure

Nuclear Technology / Volume 91 / Number 3 / September 1990 / Pages 311-344

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT90-A34455

A method for calculating the depletion and production of uranium, plutonium, transplutonium nuclides, and fission products (DPUFP) in a boiling water reactor was evaluated using measured values for JPDR-1 nuclear fuel. The results show that (a) a three-dimensional nuclear thermohydrodynamic calculation is required for an accurate estimate, (b) the void fraction of a fuel assembly has a large effect on the production of transplutonium nuclides, (c) the measured values can be applied universally by correcting the irradiation and cooling histories and the effect of the neutron spectrum, (d) more reliable DPUFPs are obtained by closely correlating the calculated value of 134Cs/137Cs with the measured values, and (e) the effective neutron cross sections of uranium and plutonium can be obtained using the measured values.