Argonne National Laboratory
Author in the following contributions
- Blind-Phase Results of the FFTF Neutronic Benchmark
- Activities of the GIF Safety and Operation Project of Sodium-Cooled Fast Reactor Systems
- Safety Analysis of the ARC-100 Sodium-Cooled Fast Reactor
- Overview of the Versatile Test Reactor Safety Analysis
- Simulation of FFTF Individual Reactivity Feedback Tests with SAS4A/SASSYS-1 Code
- BLIND PHASE RESULTS FOR TRANSIENT SIMULATIONS OF THE FFTF LOSS OF FLOW WITHOUT SCRAM TEST #13