An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

A method to determine the neutron production rate of a spent nuclear fuel segment sample by means of non-destructive assay conducted under standard controlled-area conditions is described and demonstrated. A neutron well counter designed for routine nuclear safeguards applications is applied. The me...

Full description

Bibliographic Details
Main Authors: Peter Schillebeeckx, M. Verwerft, P. Romojaro, G. Žerovnik, N. Messaoudi, G. Alaerts, L. Fiorito, K. Govers, J. Paepen, Y. Parthoens, B. Pedersen, A. Stankovskiy, G. Van den Eynde, R. Wynants
Format: Article
Language:English
Published: Frontiers Media S.A. 2023-04-01
Series:Frontiers in Energy Research
Subjects:
neutron emission
neutron correlation counting
spent nuclear fuel (SNF)
depletion calculation
spontaneous fission
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2023.1162367/full

Internet

https://www.frontiersin.org/articles/10.3389/fenrg.2023.1162367/full

Similar Items