Published 2013 | Version v1
Book

Evaluation of vectorized Monte Carlo algorithms on GPUs for a neutron Eigenvalue problem

  • 1. Nuclear Engineering Program, Rensselaer Polytechnic Institute, Troy, NY 12180 (United States)
  • 2. Monte Carlo Codes Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

Description

Conventional Monte Carlo (MC) methods for radiation transport computations are 'history-based', which means that one particle history at a time is tracked. Simulations based on such methods suffer from thread divergence on the graphics processing unit (GPU), which severely affects the performance of GPUs. To circumvent this limitation, event-based vectorized MC algorithms can be utilized. A versatile software test-bed, called ARCHER - Accelerated Radiation-transport Computations in Heterogeneous Environments - was used for this study. ARCHER facilitates the development and testing of a MC code based on the vectorized MC algorithm implemented on GPUs by using NVIDIA's Compute Unified Device Architecture (CUDA). The ARCHERGPU code was designed to solve a neutron eigenvalue problem and was tested on a NVIDIA Tesla M2090 Fermi card. We found that although the vectorized MC method significantly reduces the occurrence of divergent branching and enhances the warp execution efficiency, the overall simulation speed is ten times slower than the conventional history-based MC method on GPUs. By analyzing detailed GPU profiling information from ARCHER, we discovered that the main reason was the large amount of global memory transactions, causing severe memory access latency. Several possible solutions to alleviate the memory latency issue are discussed. (authors)

Part of:
Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
978-0-89448-700-2
Imprint Title
Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
Imprint Pagination
3016 p.
Journal Page Range
p. 2513-2522

Conference

Title
2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
Acronym
M and C 2013
Dates
5-9 May 2013
Place
Sun Valley, ID (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
45033851
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; COMPUTER CODES; COMPUTER GRAPHICS; EIGENVALUES; EVALUATION; INFORMATION; MATHEMATICAL SOLUTIONS; MONTE CARLO METHOD; NEUTRON TRANSPORT; SIMULATION; TESTING
Descriptors DEC
CALCULATION METHODS; MATHEMATICAL LOGIC; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT

Optional Information

Notes
14 refs.