Neutronics Analyses of a NERVA-derived NTP Reactor Core using Nodal Diffusion Codes

Impact of Interleaved Thermally Conductive Material with Conformal Fluid Channels on Tooling Thermal Response

Validation of Transmission Densitometry for Holdup Quantification in Salt-wetted MSR Components

What: NRE 8011/8012 Seminar Who: Dr. Christine Egnatuk, Lawrence Livermore National Laboratory When: Thursday, October 24, 2024 at 11:00 AM Where: Boggs Building Room 3-47 Title: Technical Nuclear Forensics: From a Lab Scientist’s Perspective

Robust Adversarial Reinforcement Learning for Antineutrino-based Nuclear Reactor Safeguards