Data for: Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data

Published: 26 February 2019| Version 1 | DOI: 10.17632/fyzwhpspv8.1
Kazuteru Sugino


In MA sample irradiation test data calculations, the neutron fluence during irradiation period is generally scaled by using dosimetry data in order to improve calculation accuracy. In such a case, appropriate correction is required to burnup sensitivity coefficients obtained by the conventional generalized perturbation theory because some cancellations occur in the burnup sensitivity coefficients. Therefore, a new formula for the burnup sensitivity coefficient has been derived with the consideration of the neutron fluence scaling (NFS) effect. In addition, the cross-section-induced uncertainty is evaluated by using the obtained burnup sensitivity coefficients and the covariance data based on the JENDL-4.0.



Sensitivity Analysis, Neutron Irradiation, Fast Reactor, Dosimetry Application, Perturbation Theory, Nuclear Reactor Physics