Tensor networks for solving the time-independent Boltzmann neutron transport equation

被引:3
|
作者
Truong, Duc P. [1 ]
Ortega, Mario I. [2 ]
Boureima, Ismael [1 ]
Manzini, Gianmarco [1 ]
Rasmussen, Kim O. [1 ]
Alexandrov, Boian S. [1 ]
机构
[1] Los Alamos Natl Lab, Theoret Div, Los Alamos, NM 87545 USA
[2] Los Alamos Natl Lab, Comp Computat & Stat Sci Div, Los Alamos, NM USA
关键词
Tensor network; Tensor train; Neutron transport; LINEAR-SYSTEMS; TRAIN; APPROXIMATION; MATRICES; RANK;
D O I
10.1016/j.jcp.2024.112943
中图分类号
TP39 [计算机的应用];
学科分类号
081203 ; 0835 ;
摘要
Tensor network techniques, known for their low -rank approximation ability that breaks the curse of dimensionality, are emerging as a foundation of new mathematical methods for ultra -fast numerical solutions of high -dimensional Partial Differential Equations (PDEs). Here, we present a mixed Tensor Train (TT)/Quantized Tensor Train (QTT) approach for the numerical solution of time -independent Boltzmann Neutron Transport equations (BNTEs) in Cartesian geometry. Discretizing a realistic three-dimensional (3D) BNTE by ( i ) diamond differencing in space, ( ii ) multigroup-in-energy, and ( iii ) discrete ordinates collocation in angle leads to large generalized eigenvalue problems that generally require a matrix -free approach and large computer clusters. Starting from this discretization, we construct a TT representation of the PDE fields and discrete operators, followed by a QTT representation of the TT cores. We then solve the tensorized generalized eigenvalue problem using a fixed-point scheme with tensor network optimization techniques. We validate our approach by applying the method to two examples of 3D neutron transport problems, currently solved by the Los Alamos National Laboratory PARallel TImedependent SN (PARTISN) solver. 1 We demonstrate that our TT/QTT method, executed on a standard desktop computer, leads to large compression. This allows for the storage of terrabytesized neutron angular flux eigenvectors in megabytes. Additionally, we create megabyte -sized full access TT representations of yottabyte-sized transport matrix operators. By leveraging the TT operators and solution methods, we obtain a 7500 times speedup when compared to the PARTISN solution time with an error of less than 10 -5 .
引用
收藏
页数:25
相关论文
共 15 条
  • [1] Using hermite neural networks to solve the time-independent schrodinger equation
    Pakniyat, A.
    Parand, K.
    INDIAN JOURNAL OF PHYSICS, 2023, 97 (12) : 3581 - 3587
  • [2] Symmetries of the P3 approximation to the Boltzmann neutron transport equation
    Pittman, Emily R.
    Schmidt, Emma M.
    Ramsey, Scott D.
    ANNALS OF NUCLEAR ENERGY, 2020, 144
  • [3] A Stable Method for Solving the Simplified Time-Dependent Neutron Transport Equation with Background Motion
    Xu, Longfei
    Shen, Huayun
    Wei, Junxia
    Pan, Liujun
    NUCLEAR SCIENCE AND ENGINEERING, 2022, 196 (02) : 161 - 182
  • [4] DETERMINANT METHODS FOR SOLVING NEUTRON TRANSPORT EQUATION IN UNSTRUCTURED GEOMETRY
    Wu Hongchun
    Liu Guoming
    Cao Liangzhi
    Chen Qichang
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 2, 2011, : 113 - 117
  • [5] A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation
    He, Qingming
    Fang, Chao
    Cao, Liangzhi
    Zhang, Haoyu
    NUCLEAR SCIENCE AND ENGINEERING, 2023, 197 (03) : 472 - 484
  • [6] Tensor Network Space-Time Spectral Collocation Method for Solving the Nonlinear Convection Diffusion Equation
    Adak, Dibyendu
    Danis, M. Engin
    Truong, Duc P.
    Rasmussen, Kim o.
    Alexandrov, Boian S.
    JOURNAL OF SCIENTIFIC COMPUTING, 2025, 103 (02)
  • [7] Computation of fundamental time-eigenvalue of the neutron transport equation
    Shen, Huayun
    Zhong, Bin
    Liu, Huipo
    PROGRESS IN NUCLEAR ENERGY, 2015, 85 : 624 - 630
  • [8] Coupling of first collision source method with Lattice Boltzmann Method for the solution of neutron transport equation
    Agarwal, Gaurav
    Singh, Suneet
    ANNALS OF NUCLEAR ENERGY, 2022, 175
  • [9] Calculating Time Eigenvalues of the Neutron Transport Equation with Dynamic Mode Decomposition
    McClarren, Ryan G.
    NUCLEAR SCIENCE AND ENGINEERING, 2019, 193 (08) : 854 - 867
  • [10] Solving the Neutron Transport Equation for Microreactor Modeling Using Unstructured Meshes and Exascale Computing Architectures
    Dawn, William C.
    Palmtag, Scott
    NUCLEAR SCIENCE AND ENGINEERING, 2023, 197 (12) : 3138 - 3159