- Reference report: _S. E. Skutnik and W. A. Wieselquist (2021), Assessment of ORIGEN Reactor Library Development for Pebble-Bed Reactors Based on the PBMR-400 Benchmark, [ORNL/TM-2020/1886](https://info.ornl.gov/sites/publications/Files/Pub150728.pdf), Oak Ridge National Laboratory, Oak Ridge, TN._
##### Heat Pipe Reactor (HPR):
- Model: INL Design A
@@ -40,6 +39,11 @@ reactor concepts:
- Model: Molten Salt Reactor Experient (MSRE)
- Reference report: _A. Lo, F. Bostelmann, D. Hartanto, B. Betzler, W. A. Wieselquist (2022), Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses, [ORNL/TM-2022/1844](https://info.ornl.gov/sites/publications/Files/Pub173113.pdf), Oak Ridge National Laboratory, Oak Ridge, TN._
##### Sodium-cooled Fast Reactor (SFR):
- Model: Advanced Breeder Test Reactor (ABTR)
- Reference report: _A. Shaw, F. Bostelmann, D. Hartanto, E. Walker, W. Wieselquist (2023), SCALE Modeling of the Sodium-Cooled Fast-Spectrum Advanced Burner Test Reactor, ORNL/TM-2022/2758, Oak Ridge National Laboratory, Oak Ridge, TN._
## Related presentations
Analyses based on the developed SCALE models were presented in public workshops organized by the NRC.
@@ -48,7 +52,7 @@ Information on these workshops and the presentations can be found under the foll