Open AccessSpecial yield data analyses for core analysis material key No. 6706-C-N
Author(s) -
W.H. Braymen,
Helen Smith
Publication year - 1965
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/26570
Subject(s) - mox fuel , plutonium , neptunium , burnup , nuclear reactor core , nuclear engineering , spent nuclear fuel , criticality , uranium , transuranium element , oxide , nuclear fuel , radiochemistry , nuclide , plutonium 240 , reactivity (psychology) , plutonium 239 , materials science , chemistry , nuclear chemistry , neutron , nuclear physics , physics , metallurgy , fission , engineering , medicine , alternative medicine , pathology
This document contains one table on the 95% confidence levels for the concentration of Plutonium, Uranium, Americium 241, Curium 242, and Neptunium 237 in an undisclosed material