Neutron Activation of Structural Materials of a Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive Waste Management
In order to estimate the radiological characteristics of disused dry storage systems for spent nuclear fuel, a stepwise framework to calculate neutron sources (ORIGEN-ARP), incident neutron flux and reaction rate (MCNPX), effective cross-section (hand calculation), and residual activity (ORIGEN-2) w...
Main Authors: | , |
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Format: | Article |
Language: | English |
Published: |
MDPI AG
2020-10-01
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Series: | Energies |
Subjects: | |
Online Access: | https://www.mdpi.com/1996-1073/13/20/5325 |