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2024

Evaluating the Impact of Neutron Absorber Materials on Spent Fuel Pool Rack Criticality Using OpenMC Monte Carlo Code

Buyrukcu, B., Buyrukcu, E., Litskevich, D., & Whittle, K. (2024). Evaluating the Impact of Neutron Absorber Materials on Spent Fuel Pool Rack Criticality Using OpenMC Monte Carlo Code. In Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle. American Society of Mechanical Engineers. doi:10.1115/icone31-137004

DOI
10.1115/icone31-137004
Conference Paper

2023

2022

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