Uncertainty assessment for the displacement damage of a pressurized water reactor vessel. (September 2021)

• Record Type: Journal Article
• Authors: Chen, Shengli; Bernard, David; Tamagno, Léonie; Litaize, Olivier; Blaise, Patrick
• Is Part Of: Nuclear materials and energy. Volume 28(2021)
• Publication Date: 2021-09
• Subjects: Displacement per Atom (DPA) -- Uncertainty propagation -- Reactor Pressure Vessel (RPV) -- Prompt Fission Neutron Spectra (PFNS) -- Nuclear data -- Model defect; Nuclear energy -- Periodicals; Nuclear fuels -- Periodicals; Nuclear reactors -- Materials -- Periodicals; Radioactive substances -- Periodicals; 621.4833
• DOI: 10.1016/j.nme.2021.101017
• Languages: English
• ISSNs: 2352-1791

Abstract

Abstract: The neutron irradiation-induced mechanical property change is a major challenge for nuclear materials. For a Pressurized Water Reactor (PWR), neutron irradiation embrittlement of the reactor pressure vessel is one of the most important issues that determine the whole nuclear power plant lifetime. The present work focuses thus on the uncertainty assessment for the neutron irradiation displacement damage of a PWR vessel. The uncertainties of neutron flux, nuclear data, and atomic displacement models are propagated to Displacement per Atom (DPA) rates with a special emphasis on the importance of correlation matrices. In addition to the uncertainty propagated from the threshold displacement energy, the total uncertainty of damage energy rate is about 10% (at 1 σ ), whereas the uncertainty is largely underestimated if the correlations of damage cross section and neutron flux are not considered. Apart from the complete uncertainty propagation shown in this paper, combining the damage energy rate uncertainty and the displacement threshold energy uncertainty is recommended for estimating the calculated DPA rate uncertainty. Besides the uncertainty, the biases induced by the model defects are preliminarily estimated.