Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors. (October 2018)
- Record Type:
- Journal Article
- Title:
- Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors. (October 2018)
- Main Title:
- Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors
- Authors:
- Powers, J.J.
Brown, N.R.
Mueller, D.E.
Patton, B.W.
Losa, E.
Košťál, M. - Abstract:
- Highlights: SCALE sensitivity and uncertainty analysis tools model LR-0 experiments with MSRE FLiBe salt insertion zones. S/U results for LR-0 FLiBe experiments compared to relevant MSR and FHR models. Key sensitivity and uncertainties discussed for LR-0 FLiBe, MSR, and FHR models. LR-0 FLiBe experiments found to match well with LEU-fueled MSR and FHR models. Abstract: Critical experiments using an insertion zone with FLiBe salt performed at the LR-0 reactor at Research Centre Řež (RC Řež) have been compared to application models for solid-fueled, fluoride-salt-cooled high-temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts using sensitivity and uncertainty (S/U) analysis techniques. These experiments support FHR and MSR advanced reactor concepts by informing on neutron spectral effects and nuclear data uncertainties related to fluoride salts. The FLiBe salt in the LR-0 experiments is from the Oak Ridge National Laboratory Molten Salt Reactor Experiment and is enriched to greater than 99.99% 7 Li. This work is part of a broader collaboration between the United States and the Czech Republic on MSR and FHR technology. Results from the S/U analyses for FHR and MSR models indicated the most significant potential source of eigenvalue bias due to nuclear data within the FLiBe salt is radiative capture in 7 Li. Other smaller but potentially significant contributions come from 19 F, 6 Li, and other 7 Li reactions. Similarity comparisons of the RC Řež LR-0Highlights: SCALE sensitivity and uncertainty analysis tools model LR-0 experiments with MSRE FLiBe salt insertion zones. S/U results for LR-0 FLiBe experiments compared to relevant MSR and FHR models. Key sensitivity and uncertainties discussed for LR-0 FLiBe, MSR, and FHR models. LR-0 FLiBe experiments found to match well with LEU-fueled MSR and FHR models. Abstract: Critical experiments using an insertion zone with FLiBe salt performed at the LR-0 reactor at Research Centre Řež (RC Řež) have been compared to application models for solid-fueled, fluoride-salt-cooled high-temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts using sensitivity and uncertainty (S/U) analysis techniques. These experiments support FHR and MSR advanced reactor concepts by informing on neutron spectral effects and nuclear data uncertainties related to fluoride salts. The FLiBe salt in the LR-0 experiments is from the Oak Ridge National Laboratory Molten Salt Reactor Experiment and is enriched to greater than 99.99% 7 Li. This work is part of a broader collaboration between the United States and the Czech Republic on MSR and FHR technology. Results from the S/U analyses for FHR and MSR models indicated the most significant potential source of eigenvalue bias due to nuclear data within the FLiBe salt is radiative capture in 7 Li. Other smaller but potentially significant contributions come from 19 F, 6 Li, and other 7 Li reactions. Similarity comparisons of the RC Řež LR-0 experiments and FHR and MSR application models indicate that the LR-0 FLiBe experiments could be useful as candidate benchmarks for low-enriched uranium–fueled application models. However, sensitivity differences observed included both spectral effects, due to the LR-0 reactor being moderated by water instead of graphite and fluoride salt, and sensitivity magnitude effects driven by the amount of FLiBe inserted and its location. New experiments with refined designs to increase the volume and importance of salt in the system could provide improved data. Results also demonstrate that salt systems using thorium and/or 233 U fuel will require additional experiments with relevant driver fuels. Increased contributions from the graphite moderator and 19 F and covariance between reactions such as 233 U fission and 233 U radiative capture indicate higher uncertainty contributions from the salt and significant differences in contributions from the fuel species due to underlying uncertainties in their nuclear data. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 120(2018)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 120(2018)
- Issue Display:
- Volume 120, Issue 2018 (2018)
- Year:
- 2018
- Volume:
- 120
- Issue:
- 2018
- Issue Sort Value:
- 2018-0120-2018-0000
- Page Start:
- 319
- Page End:
- 332
- Publication Date:
- 2018-10
- Subjects:
- Nuclear -- Reactor -- Molten salt -- MSR -- FHR -- Sensitivity -- Uncertainty -- LR-0 -- Experiment -- FLiBe
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2018.05.052 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 13012.xml