MOX fuel uses a combination of UO2 and PuO2 in their fuel pellets. Calculate the macroscopic neutron
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MOX fuel uses a combination of UO2 and PuO2 in their fuel pellets. Calculate the macroscopic neutron absorption cross-section of MOX fuel load with 7w/o Pu-239. Assume all Pu present is Pu-239, with natural uranium for the remainder. Assume non 1/v behavior and use a fuel temperature of 600 deg C.
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ISBN: 978-1412964746
1st edition
Authors: Robert M. Schindler
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