Papers
To access paper attachments, you must be logged in and registered for the meeting.
Study of Effect of PWR Cold Leg Temperature Gradient on Reactor Core Condition
Comparisons of Nodal Diffusion and Whole-Core Transport Methods for Multiple Cycles of a Small Light Water Reactor
Determination of the Spent Fuel Decay Heat with the VERA Core Simulator
VERA Neutronics High-Fidelity Benchmark for a Modern PWR Core Design
Discussion
To join the conversation, you must be logged in and registered for the meeting.