Abstract
A reactor core physics module is being developed for a framework to test MC&A methods on a variety of MSR designs. The module utilizes collapsed one-group reactor data libraries that can be interpolated. These data libraries were generated for a generic thermal fluoride molten salt reactor design. The parameter spacing and interpolation error of these data libraries was calculated.
| Original language | English |
|---|---|
| Pages (from-to) | 339-342 |
| Number of pages | 4 |
| Journal | Transactions of the American Nuclear Society |
| Volume | 121 |
| DOIs | |
| State | Published - 2019 |
| Externally published | Yes |
| Event | 2019 Transactions of the American Nuclear Society, ANS 2019 - Washington, United States Duration: Nov 17 2019 → Nov 21 2019 |
Funding
This work was supported by a Nuclear Energy University Programs (NEUP) grant sponsored by the U.S. Department of Energy, Office of Nuclear Energy, award number DENE0008793.
| Funders | Funder number |
|---|---|
| Nuclear Energy University Programs | |
| U.S. Department of Energy | |
| Office of Nuclear Energy | DENE0008793 |