Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE
The Very High Temperature Critical Assembly (VHTRC) experiment represents one of the few data sets available for the validation of HTGR lattice physics. Within the framework of the IAEA Coordinated Research Project on HTGR Uncertainty Analysis in Modeling, uncertainty and sensitivity analyses of this graphitemoderated facility are performed as the validation reference to the prismatic MHTGR350 fuel block calculations. Nominal multigroup and continuousenergy criticality calculations with the KENOVI Monte Carlo code of the SCALE code package are compared with the continuousenergy Monte Carlo Code Serpent. Good agreement with a maximum difference of 250 pcm is obtained. The experimental data set, however, differs by several hundred pcm with the results of both codes when using the ENDFVII.0 library. When using ENDF/BVII.1 data, this difference is reduced to a few hundred pcm and the calculations lie within the experimental error bars. Uncertainties of the VHTRC multiplication factors due to uncertainties in nuclear data are determined with SAMPLER/KENOVI of SCALE 6.2 and with continuousenergy TSUNAMI of SCALE 6.2. For all experimental configurations, the obtained uncertainty is found to be 0.58% when using ENDF/BVII.0 data. The top contributor to this uncertainty is the average number of neutrons per fission event of U235. With ENDF/BVII.1more »
 Authors:

^{[1]}
;
^{[2]}
 Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)
 Idaho National Lab. (INL), Idaho Falls, ID (United States)
 Publication Date:
 Report Number(s):
 INL/JOU1742606Rev000
Journal ID: ISSN 03064549
 Grant/Contract Number:
 AC0705ID14517
 Type:
 Accepted Manuscript
 Journal Name:
 Annals of Nuclear Energy (Oxford)
 Additional Journal Information:
 Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 110; Journal Issue: C; Journal ID: ISSN 03064549
 Publisher:
 Elsevier
 Research Org:
 Idaho National Lab. (INL), Idaho Falls, ID (United States)
 Sponsoring Org:
 USDOE Office of Nuclear Energy (NE)
 Country of Publication:
 United States
 Language:
 English
 Subject:
 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; HTGR; VHTRC; SCALE
 OSTI Identifier:
 1474117
Bostelmann, Friederike, and Strydom, Gerhard. Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE. United States: N. p.,
Web. doi:10.1016/j.anucene.2017.06.052.
Bostelmann, Friederike, & Strydom, Gerhard. Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE. United States. doi:10.1016/j.anucene.2017.06.052.
Bostelmann, Friederike, and Strydom, Gerhard. 2017.
"Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE". United States.
doi:10.1016/j.anucene.2017.06.052. https://www.osti.gov/servlets/purl/1474117.
@article{osti_1474117,
title = {Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE},
author = {Bostelmann, Friederike and Strydom, Gerhard},
abstractNote = {The Very High Temperature Critical Assembly (VHTRC) experiment represents one of the few data sets available for the validation of HTGR lattice physics. Within the framework of the IAEA Coordinated Research Project on HTGR Uncertainty Analysis in Modeling, uncertainty and sensitivity analyses of this graphitemoderated facility are performed as the validation reference to the prismatic MHTGR350 fuel block calculations. Nominal multigroup and continuousenergy criticality calculations with the KENOVI Monte Carlo code of the SCALE code package are compared with the continuousenergy Monte Carlo Code Serpent. Good agreement with a maximum difference of 250 pcm is obtained. The experimental data set, however, differs by several hundred pcm with the results of both codes when using the ENDFVII.0 library. When using ENDF/BVII.1 data, this difference is reduced to a few hundred pcm and the calculations lie within the experimental error bars. Uncertainties of the VHTRC multiplication factors due to uncertainties in nuclear data are determined with SAMPLER/KENOVI of SCALE 6.2 and with continuousenergy TSUNAMI of SCALE 6.2. For all experimental configurations, the obtained uncertainty is found to be 0.58% when using ENDF/BVII.0 data. The top contributor to this uncertainty is the average number of neutrons per fission event of U235. With ENDF/BVII.1 data, uncertainties of about 0.66% are obtained in particular due to an increased uncertainty of U235 nubar in the latest ENDF release. In conclusion, when considering these nuclear data uncertainties, the obtained 1s uncertainty intervals are overlapping with the experimental error bars.},
doi = {10.1016/j.anucene.2017.06.052},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 110,
place = {United States},
year = {2017},
month = {7}
}