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

Jacob Smith (Georgia Tech), Dan Kotlyar (Georgia Tech)

Paper

Clarification on the Various Methods of Calculating the P1 Transport Cross Section Using Monte Carlo Codes

1:25–1:50PM MDT

Vidor H. Lujan (Georgia Tech), Bailey Painter (Georgia Tech), Dan Kotlyar (Georgia Tech)

Paper

Multigroup Cross Section Generation with the Shift Monte Carlo Code

1:50–2:15PM MDT

Tara Pandya (ORNL), Friederike Bostelmann (ORNL), Donny Hartanto (ORNL), Steven Hamilton (ORNL), Matthew Jessee (ORNL), Nicholas Luciano (ORNL), Tarek Ghaddar (ORNL)

Paper

Implementation of the Iterated Fission Probability Method in OpenMC to Compute Adjoint-Weighted Kinetics Parameters

2:15–2:40PM MDT

Joffrey Dorville (ANL), Luke Labrie-Cleary (Copenhagen Atomics), Paul K. Romano (ANL)

Paper