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

• Published in: Annals of nuclear energy Vol. 130; pp. 118 - 123
• Main Authors: Sugino, Kazuteru, Numata, Kazuyuki, Ishikawa, Makoto, Takeda, Toshikazu
• Format: Journal Article
• Language: English
• Published: Elsevier Ltd 01-08-2019
• Subjects: Burnup sensitivity coefficient; Dosimeter; JENDL-4.0; MA sample; Neutron fluence scaling; Uncertainty; JENDL-4.0; Dosimeter; Uncertainty; Burnup sensitivity coefficient; MA sample; Neutron fluence scaling
• ISSN: 0306-4549; 1873-2100
• DOI: 10.1016/j.anucene.2019.02.035

•Modified burnup sensitivity coefficients for sample irradiation test data calculation.•Effectiveness for validation and improvement of the minor actinide cross-section.•Taking into account the neutron fluence scaling due to the dosimetry data utilization.•Rationalization of the cross-section-induced uncertainty for its quantification.
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.