Beta-effective sensitivity and uncertainty analysis of MYRRHA reactor for possible use in nuclear data validation and improvement

摘要

New reactor concept studies, such as those of the MYRRHA Accelerator Driven System (ADS), with their extended nuclear data needs relaunched the interest in sensitivity and uncertainty (S/U) studies. S/U analysis play an essential role in assuring the accuracy and reliability of nuclear reactor computations and provide an insight in the physical phenomena involved in the neutron transport. This paper presents the study of the MYRRHA critical core, which is designed to operate at 100 MW thermal power. The previously presented analysis of the MYRRHA effective multiplication factor (k(eff)) was extended to study the sensitivity and uncertainty in kinetic parameters, such as the effective delayed neutron fraction (beta(eff)). The sensitivity and uncertainty computations were performed by means of the SUSD3D code based on forward and adjoint-flux first-order perturbation theory. The sensitivity coefficients of beta(eff) with respect to the basic nuclear data were calculated by the k-ratio derivation method proposed in 2011. The main components of the uncertainties in beta(eff) were estimated using the JENDL-4.0u covariance data. The energy dependent sensitivity profiles of k(eff) and beta(eff) with respect to nuclear data are compared in view of exploiting the differences among them for a physically more complete, comprehensive and consistent nuclear data validation and improvement procedure. The accuracy of the k(eff) and beta(eff) measurements and calculations has to be carefully evaluated in order to conclude on the nuclear data status and possible improvements. (C) 2017 Elsevier Ltd. All rights reserved.