Abstract
This study was conducted to validate the SCALE/Polaris v6.3.0–PARCS v3.4.2 code procedure with the Evaluated Nuclear Data File (ENDF)/B-VII.1 AMPX 56-group library for pressurized water reactor (PWR) analysis, by comparing simulated results with measured data for critical experiments and operating PWRs. Uncertainties of the SCALE/Polaris–PARCS code procedure for PWR analysis were evaluated in the validation for the PWR key nuclear parameters such as critical boron concentrations, reactivity, control bank work, temperature coefficients, and pin and assembly power peaking factors.
| Original language | English |
|---|---|
| Pages (from-to) | 246-259 |
| Number of pages | 14 |
| Journal | Journal of Nuclear Engineering |
| Volume | 5 |
| Issue number | 3 |
| DOIs | |
| State | Published - Sep 2024 |
Funding
This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or repro-duce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). This research was funded by the US Nuclear Regulatory Commission Office of Research contract number 31310019N0008.
| Funders | Funder number |
|---|---|
| U.S. Department of Energy | |
| U.S. Nuclear Regulatory Commission | 31310019N0008 |
| U.S. Nuclear Regulatory Commission |
Keywords
- AMPX 56-group library
- ENDF/B-VII.1
- PARCS
- pressurized water reactor
- SCALE/Polaris
- validation