An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part I: Flux and Eigenvalue Solutions. (3rd August 2021)
- Record Type:
- Journal Article
- Title:
- An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part I: Flux and Eigenvalue Solutions. (3rd August 2021)
- Main Title:
- An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part I: Flux and Eigenvalue Solutions
- Authors:
- Sobes, Vladimir
Ducru, Pablo
Alhajri, Abdulla
Ganapol, Barry
Forget, Benoit - Abstract:
- Abstract: Computing in the energy dimension is one of the greatest challenges confronting present-day deterministic neutron transport solvers. Accurately resolving the neutron flux as neutrons downscatter across resonances in the nuclear cross sections currently requires considerable computing power and suffers from approximation errors. Flux uncertainty resulting from the uncertainty of the resonance structure is the single-largest cause of reactivity uncertainty. Any additional reference solution for the critical neutron downscattering problem with resonance phenomena would be a boon to verification and validation of neutronics codes. This paper establishes a benchmark to verify the accuracy of neutron transport criticality solvers along the energy dimension. For the first time, the analytic solution of the flux amplitude is derived in the particular case of an infinite homogeneous medium with isotropic scattering in the center of mass and an arbitrary number of no-threshold, neutral particle reaction resonances (e.g., radiative capture, fission, and resonance scattering). Original analytic expressions are established to quantify the discrepancy between the ψ k ( E ) and ψ α ( E ) flux amplitudes, respective solutions of the multiplication factor k, or the exponential time-evolution frequency α eigenproblems. The physical study of these relations led to analysis of their first-order relative difference near the criticality condition α = 0 . Finally, numerical solutions areAbstract: Computing in the energy dimension is one of the greatest challenges confronting present-day deterministic neutron transport solvers. Accurately resolving the neutron flux as neutrons downscatter across resonances in the nuclear cross sections currently requires considerable computing power and suffers from approximation errors. Flux uncertainty resulting from the uncertainty of the resonance structure is the single-largest cause of reactivity uncertainty. Any additional reference solution for the critical neutron downscattering problem with resonance phenomena would be a boon to verification and validation of neutronics codes. This paper establishes a benchmark to verify the accuracy of neutron transport criticality solvers along the energy dimension. For the first time, the analytic solution of the flux amplitude is derived in the particular case of an infinite homogeneous medium with isotropic scattering in the center of mass and an arbitrary number of no-threshold, neutral particle reaction resonances (e.g., radiative capture, fission, and resonance scattering). Original analytic expressions are established to quantify the discrepancy between the ψ k ( E ) and ψ α ( E ) flux amplitudes, respective solutions of the multiplication factor k, or the exponential time-evolution frequency α eigenproblems. The physical study of these relations led to analysis of their first-order relative difference near the criticality condition α = 0 . Finally, numerical solutions are provided to a benchmark problem constituted of the first resonance of 239 Pu, the 6.67-eV resonance of 238 U, and a scattering isotope with a flat cross section, allowing for the computational verification of the energy resolution of current neutron transport criticality codes. Through these novel results, this analytic benchmark can serve as a reference to verify the energy resolution and sensitivity analysis of neutron transport criticality calculations. … (more)
- Is Part Of:
- Nuclear science and engineering. Volume 195:Number 8(2020)
- Journal:
- Nuclear science and engineering
- Issue:
- Volume 195:Number 8(2020)
- Issue Display:
- Volume 195, Issue 8 (2020)
- Year:
- 2020
- Volume:
- 195
- Issue:
- 8
- Issue Sort Value:
- 2020-0195-0008-0000
- Page Start:
- 795
- Page End:
- 812
- Publication Date:
- 2021-08-03
- Subjects:
- Neutron transport -- neutron slowing down -- nuclear cross-section resonances -- resonance self-shielding -- analytic benchmark
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
Nuclear energy
Nuclear engineering
Periodicals
539.705 - Journal URLs:
- http://www.ans.org/pubs/journals/nse/ ↗
http://www.tandfonline.com/toc/unse20/current?nav=tocList ↗
http://www.tandfonline.com/ ↗ - DOI:
- 10.1080/00295639.2021.1874777 ↗
- Languages:
- English
- ISSNs:
- 0029-5639
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 18247.xml