Simulation of low-enriched uranium burnup in Russian VVER-1000 reactors with the Serpent Monte-Carlo code

Simulation of low-enriched uranium burnup in Russian VVER-1000 reactors with the Serpent Monte-Carlo code

This work deals with the assessment of the burnup capabilities of the Serpent Monte Carlo code to predict spent nuclear fuel (SNF) isotopic concentrations for low-enriched uranium (LEU) fuel at different burnup levels up to 47 MWd/kgU. The irradiation of six UO2 experimental samples in three differe...

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Bibliographic Details
Main Authors: L. Mercatali, N. Beydogan, V.H. Sanchez-Espinoza
Format: Article
Language:English
Published: Elsevier 2021-09-01
Series:Nuclear Engineering and Technology
Subjects:
Spent fuel
Burnup calculation
Monte Carlo
Nuclear data libraries
VVER
Online Access:http://www.sciencedirect.com/science/article/pii/S173857332100156X

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