Papers
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A Hybrid Cross Section Generation Method Using Monte Carlo Codes for Nuclear Thermal Propulsion Nodal Diffusion Analysis
1:00–1:25PM MDT
Clarification on the Various Methods of Calculating the P1 Transport Cross Section Using Monte Carlo Codes
1:25–1:50PM MDT
Multigroup Cross Section Generation with the Shift Monte Carlo Code
1:50–2:15PM MDT
Implementation of the Iterated Fission Probability Method in OpenMC to Compute Adjoint-Weighted Kinetics Parameters
2:15–2:40PM MDT
Discussion
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