Abstract
This paper investigates the impact of porosity misrepresentation in ENDF/B-VIII.1 graphite thermal scattering law (TSL) evaluations on reactor criticality.Our studies involve inelastic neutron scattering (INS) measurements, transmission measurements, and nuclear criticality calculations.The INS measurements contradict the current TSL assumptions, showing no significant porosity dependence.Transmission measurements reveal discrepancies between TSL predictions and experimental data, highlighting the need for inclusion of small angle neutron scattering (SANS) cross sections.Criticality calculations for various reactor benchmarks (HTR-10, HTTR, and PROTEUS) indicate substantial overestimation in effective multiplication factor (ke f f ) for porous graphite ENDF/B-VIII.1 TSLs due to these porosity modeling inaccuracies.Our research suggests revising current neutron scattering physics to incorporate SANS modeling, to account for accurate treatment of porosity in nuclear graphite, vital for reliable designs of advanced nuclear reactor designs.
| Original language | English |
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| Title of host publication | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 |
| Publisher | American Nuclear Society |
| Pages | 1527-1538 |
| Number of pages | 12 |
| ISBN (Electronic) | 9780894487972 |
| DOIs | |
| State | Published - 2024 |
| Event | 2024 International Conference on Physics of Reactors, PHYSOR 2024 - San Francisco, United States Duration: Apr 21 2024 → Apr 24 2024 |
Publication series
| Name | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 |
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Conference
| Conference | 2024 International Conference on Physics of Reactors, PHYSOR 2024 |
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| Country/Territory | United States |
| City | San Francisco |
| Period | 04/21/24 → 04/24/24 |
Funding
This work was supported by the Nuclear Criticality Safety Program, funded and managed by the National Nuclear Security Administration, United States for the Department of Energy.This work was supported by the US Nuclear Regulatory Commission (NRC).This research used resources at the Spallation Neutron Source, a DOE Office of Science User Facility operated by the Oak Ridge National Laboratory.This research used resources of the National Energy Research Scientific Computing Center, a DOE SC user facility operated under Contract No.DE-AC02-05CH11231.
Keywords
- TSL
- criticality
- nuclear graphite
- porosity
- reactor benchmarks