Abstract
As the new ENDF/B-VIII.0 data has continued development from its initial beta release into the final release version, it has subsequently undergone processing and testing at Oak Ridge National Laboratory with AMPX and SCALE. Each of the beta releases has been processed with AMPX to create both multigroup (MG) and continuous-energy (CE) libraries. The MG libraries were all processed using the SCALE 252-group structure. These libraries were then used with the VALID suite for benchmarking the new data library’s performance against the currently distributed ENDF/B-VII.1 (VII.1)-based SCALE libraries. Here, we compare the MG and CE VALID results for the two current ENDF releases, versions VII.1 and the most recent beta release of ENDF/B-VIII.0 as of this writing (VIII.0.4). Generally, both the MG and CE VALID aggregate results for VIII.0. 4 compare reasonably well with their VII.1-derived counterparts. As can be expected of any new ENDF release, some of the individual cases have substantially different computed neutron multiplicity () values between the two releases, although typically the differences are less than 100 percent-milli (pcm). However, changes to the plutonium cross sections have induced much larger changes in the ratio of the computed to the experimental value (C/E) for thermal spectrum plutonium solution critical systems. This paper details the comparative performance of the VII.1 and VIII.0.4 data for the broad range of test cases covered by the VALID suite. A companion paper at this conference provides details of the baseline validation of SCALE 6.2, including the first release of the VII.1 data.
| Original language | English |
|---|---|
| Title of host publication | ANS NCSD - 2017 Nuclear Criticality Safety Division Topical Meeting |
| Subtitle of host publication | Criticality Safety - Pushing Boundaries by Modernizing and Integrating Data, Methods, and Regulations |
| Publisher | American Nuclear Society |
| ISBN (Electronic) | 9780894487408 |
| State | Published - 2017 |
| Event | 2017 Nuclear Criticality Safety Division Topical Meeting: Criticality Safety - Pushing Boundaries by Modernizing and Integrating Data, Methods, and Regulations, NCSD 2017 - Carlsbad, United States Duration: Sep 10 2017 → Sep 15 2017 |
Publication series
| Name | ANS NCSD - 2017 Nuclear Criticality Safety Division Topical Meeting: Criticality Safety - Pushing Boundaries by Modernizing and Integrating Data, Methods, and Regulations |
|---|---|
| Volume | 2017-September |
Conference
| Conference | 2017 Nuclear Criticality Safety Division Topical Meeting: Criticality Safety - Pushing Boundaries by Modernizing and Integrating Data, Methods, and Regulations, NCSD 2017 |
|---|---|
| Country/Territory | United States |
| City | Carlsbad |
| Period | 09/10/17 → 09/15/17 |
Funding
* This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy 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).
Keywords
- ENDF
- Neutron cross sections
- Nuclear data processing