Abstract
The Evaluated Nuclear Data File (ENDF)/B-VIII.0 data library was released in 2018. To assess the new data during development and shortly after release, many validation calculations were performed with static, room-temperature benchmarks. Recently, when performing validation of ENDF/B-VIII.0 for pressurized water reactor depletion calculations, a regression in performance compared to ENDF/B-VII.1 was observed. This paper documents extensive benchmark calculations for light-water reactors performed using continuous energy Monte Carlo code with ENDF/B-VII.1 and -VIII.0 and neutronic characteristics of ENDF/B-VIII.0 are discussed and compared to those of ENDF/B-VII.1. It is our recommendation that ENDF/B data library assessment should include reactor-specific benchmark assessments, including depletion cases, such that these types of regressions may be caught earlier in the data development cycle.
| Original language | English |
|---|---|
| Pages (from-to) | 318-335 |
| Number of pages | 18 |
| Journal | Journal of Nuclear Engineering |
| Volume | 2 |
| Issue number | 4 |
| DOIs | |
| State | Published - Dec 2021 |
Funding
This research was supported by the US Nuclear Regulatory Commission Office of Research and the US Department of Energy NEAMS project. This research was funded by the US Nuclear Regulatory Commission Office of Research with the agreement number 31310019N0008 for the SCALE code development, assessment and maintenance.
| Funders | Funder number |
|---|---|
| US Nuclear Regulatory Commission Office of Research | |
| U.S. Department of Energy | |
| U.S. Nuclear Regulatory Commission | 31310019N0008 |
| U.S. Nuclear Regulatory Commission |
Keywords
- benchmark calculation
- ENDF/B-VII.1 and VIII.0
- light water reactor
- neutronic characteristics