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Covariance matrices were estimated for the fission and capture cross sections and the numbers of neutrons per fission of 237Np, 241Am and 243Am given in JENDL-3.3. GMA and KALMAN codes were applied to estimate them for the fission and capture cross sections, respectively. In the low energy region, the errors of resonance parameters were given. The covariance matrices for the numbers of prompt neutrons per fission (Vp ) were evaluated by assuming a linear equation. For the delayed neutrons (vd ), only their standard deviations were estimated. The results were compiled in the ENDF-6 format and merged with JENDL-3.3.
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Tsuneo NAKAGAWA (2005) studied this question.
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