Abstract
The SCALE/Polaris–PARCS code procedure has been used in the confirmatory analysis for boiling water reactors by the US Nuclear Regulatory Commission. In this study, 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 was validated by comparing the simulated results with the measured data for operating boiling water reactors, including Peach Bottom Unit 2 cycles 1–3, Hatch Unit 1 cycles 1–3, and Quad Cities Unit 1 cycles 1–3. The uncertainties and biases of the SCALE/Polaris–PARCS code package for boiling water reactor physics analysis were evaluated in the validation for key nuclear parameters such as reactivity and traversing in-core probe data.
| Original language | English |
|---|---|
| Pages (from-to) | 260-273 |
| 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 reproduce 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
- SCALE/Polaris
- boiling water reactor
- validation