Code RADUGA T for Simulating Neutrons Fluxes in Nuclear Power Stations

Olga V. Nikolaeva, Sergey A. Gaifulin, Leonid P. Bass

Abstract


Design and operation of nuclear power stations (NPS) are followed by simulation of neutron propagation in these stations. It is necessary to consider borders of multi-scale structural elements consisting of different materials. It is desirable to use parallel computer because of big size of NPSs. To keep such conditions, algorithms and codes for solving the integro-differential transport equation on unstructured grids are being developed. In the paper such algorithms included into the code RADUGA T are outlined. Grids, grid schemes, iterative methods to solve grid equations are presented. Calculation parallelization methods for hybrid computers are considered, MPI and OpenMP techniques are used. Methods of building, improvement, decomposition and visuzlisation of spatial grids are considered. Software implementation is described. The algorithms of the code RADUGA T are compared with methods of other codes. Computation parallelization efficiency study results are presented. The problem of neutron multiplication factor calculation in a light-water reactor model is solved. The multi-processor computer MVS-10P of the Joint SuperComputernal Center is used. Acceleration of each algorithm being used and summary acceleration are given.


Keywords


transport equation; unstructured frids; grid schemes; iteration methods; parallel calculation

References


Bass L.P., Voloschenko A.M., Germogenova T.A. Discrete Ordinate Method in Radiation Transport Problem. Moscow, KIAM Press, 1986. 231 p. (in Russian)

Belousov V.I., Grushin N.A., Sychugova E.P., et al. Some Results of Verification of Code ODETTA for Shielding Calculations. Nuclear Science and Technology: Nuclear Reactor Physics. 2018. No. 3. P. 46–53. (in Russian)

Kokonkov N.I., Nikolaeva O.V. An iterative KP1 Method for Solving the Transport Equation in 3D Domains on Unstructured Grids. Computational Mathematics and Mathematical Physics. 2015. Vol. 55, no. 10. P. 1698–1712. DOI: 10.7868/S0044466915100154.

Nikolaev A.A., Usenkov V.V., Afanasiev P.B., et al. Actual State of Development of the Software for Radiation Transport Calculatons in Core and Shield of Reactor Facities with Lead-Bismuth Coolant. Nuclear Science and Technology: Nuclear Reactor Physics. 2017. No. 1. P. 143–147. (in Russian)

Nikolaev A.A. Improvement of Geometric Options of SN-code PMSNSYS-II. Nuclear Science and Technology: Nuclear Reactor Physics. 2017. No. 1. P. 129–143. (in Russian)

Nikolaeva O.V., Gaifulin S.A., Bass L.P. On decomposition of a unstructured grid to solving the neutron transport equation on parallel computers. Parallel Computational Technologies (PCT'2019): Proceedings of the International Scientific Conference (Kaliningrad, Russia, April, 2–4, 2019). Chelyabinsk, Publishing of the South Ural State University, 2019. P. 362–372. (in Russian)

Nikolaeva O.V., Gaifulin S.A., Bass L.P. Detailed Simulation of Winfrith IRON 88 Benchmark (ASPIS) in (r, z)- and (x, y, z)-Geometries. Izvestiya vuzov. Yadernaya Energetika. 2019. No. 3. P. 135–147. DOI: 10.26583/npe.2019.3.12. (in Russian)

Nikolaeva O.V., Kazantseva A.S. Comparison Between the Properties of Grid Schemes for Solving the Transport Equation on Unstructured Thetrahedral Grids. Nuclear Science and Technology. Series: Mathematical Modeling of Physical Processes. 2019. No. 1. P. 3–18. (in Russian)

Nikolaeva O.V., Kazantseva A.S. Accuracy of FEM Schemes for Solving the Transport Equation on Unstructured Thetrahedral and Prismatic Grids. Nuclear Science and Technology. Series: Mathematical Modeling of Physical Processes. 2020. No. 1. P. 3–19. (in Russian)

Seleznev E.F., Bereznev V.P. Using the Diffusive Approximation for Reactor with Cavities Calculation. Izvestiya Vuzov. Yadernaya Energetika. 2018. No. 2. P. 66–67. DOI: 10.26583/npe.2018.2.07. (in Russian)

Vassiliev O.D., Wareing T.A., Davis I.M., et al. Feasibility of a Multigroup Deterministic Solution Method for 3D Radiotherapy Dose Calculations. International Journal of Radiative Oncology, Biology, Physics. 2008. Vol. 72. P. 220–227. DOI: 10.1016/j.ijrobp.2008.04.0572017.

Chen Y., Zhang B., Zhang L., et al. ARES: A Parallel Discrete Ordinates Transport Code for Radiation Shielding Applications and Reactor Physics Analysis. Hindawi Science and Technology of Nuclear Installations. 2017. Article ID 2596727. DOI: 10.1155/2017/2596727.

Colomer G., Borrell R., Trias F.X., et al. Parallel Algorithms for Sn Transport Sweeps on Unstructured Meshes. Journal of Computational Physics. 2013. Vol. 232. P. 118–135. DOI: 10.1016/j.jcp.2012.07.009.

Kim J.W., Lee Y.O. A Deep Penetration Problem Calculation Using AETIUS: An Easy Modeling Discrete Ordinates Transport Code UsIng Unstructured Tetrahedral Mesh, Shared Memory Parallel. EPJ Web of Conferences. 2017. Vol. 153. P. 06025. DOI: 10.1051/epjconf/20171530.

Lenain R., Masiello E., Damian F., Sanchez R. Domain Decomposition Method for 2D and 3D Transport Calculations Using Hybrid MPI/OPENMP Parallelelizm. Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method: Proceedings of the Joint International Conference (Nashville, Tennessee, April, 19–23, 2015). LaGrange Park, IL, American Nuclear Society, 2015. URL: https://halcea.archives-ouvertes.fr/cea-02506817/document (accessed: 14.09.2020).

Pautz Sh.D. An Algorithm for Parallel Sn Sweeps on Unstructured Meshes. Nuclear Science and Engineering. 2002. Vol. 140, no. 2. P. 111–136. DOI: 10.13182/NSE02-1.

Plimpton S.J., Hendrickson B., Burns Sh.P., et al. Parallel Sn Sweeps on Unstructured Grids: Algorithms for Prioritization, Grid Partitioning, and Cycle Detection. Nuclear Science and Engineering. 2005. Vol. 150. P. 267–283. DOI: 10.13182/NSE150-267.

Takeda T., Ikeda H. 3-D Neutron Transport Benchmarks. Journal of Nuclear Science and Technology. 1991. Vol. 28, no. 7. P. 656–669. DOI: 10.3327/jnst.28.656.

Vega R.M., Adams M.L. Transport Sweeps Using an Improved Slice Balance Approach with LDFE and GPU Acceleration. Mathematics & Computational Methods Applied to Nuclear Science & Engineering: Procedeengs of the International Conference (Jeju, Korea, April, 16–20, 2017). URL: https://www.kns.org/files/int_paper/paper/MC2017_2017_1/P056S01-11VegaR.pdf (accessed: 14.09.2020).

Yessayan R., Azmy Y., Schunert S. Development Of A Parallel Performance Model For The THOR Neutral Particle Transport Code. Mathematics & Computational Methods Applied to Nuclear Science & Engineering: Procedeengs of the International Conference (Jeju, Korea, April, 16–20, 2017). URL: https://www.osti.gov/servlets/purl/1369430 (accessed: 14.09.2020).

Adaptive Numerical Instruments 3D. URL: https://sf.net/p/ani3d/ (accessed: 14.09.2020).




DOI: http://dx.doi.org/10.14529/cmse210106