TY - GEN
T1 - Improved mesh based photon sampling techniques for neutron activation analysis
AU - Relson, Eric
AU - Wilson, Paul P.H.
AU - Biondo, Elliott D.
PY - 2013
Y1 - 2013
N2 - The design of fusion power systems requires analysis of neutron activation of large, complex volumes, and the resulting particles emitted from these volumes. Structured mesh-based discretization of these problems allows for improved modeling in these activation analysis problems. Finer discretization of these problems results in large computational costs, which drives the investigation of more efficient methods. Within an ad hoc subroutine of the Monte Carlo transport code MCNP, we implement sampling of voxels and photon energies for volumetric sources using the alias method. The alias method enables efficient sampling of a discrete probability distribution, and operates in 0(1) time, whereas the simpler direct discrete method requires 0(log(n)) time. By using the alias method, voxel sampling becomes a viable alternative to sampling space with the 0(1) approach of uniformly sampling the problem volume. Additionally, with voxel sampling it is straightforward to introduce biasing of volumetric sources, and we implement this biasing of voxels as an additional variance reduction technique that can be applied. We verify our implementation and compare the alias method, with and without biasing, to direct discrete sampling of voxels, and to uniform sampling. We study the behavior of source biasing in a second set of tests and find trends between improvements and source shape, material, and material density. Overall, however, the magnitude of improvements from source biasing appears to be limited. Future work will benefit from the implementation of efficient voxel sampling - particularly with conformai unstructured meshes where the uniform sampling approach cannot be applied.
AB - The design of fusion power systems requires analysis of neutron activation of large, complex volumes, and the resulting particles emitted from these volumes. Structured mesh-based discretization of these problems allows for improved modeling in these activation analysis problems. Finer discretization of these problems results in large computational costs, which drives the investigation of more efficient methods. Within an ad hoc subroutine of the Monte Carlo transport code MCNP, we implement sampling of voxels and photon energies for volumetric sources using the alias method. The alias method enables efficient sampling of a discrete probability distribution, and operates in 0(1) time, whereas the simpler direct discrete method requires 0(log(n)) time. By using the alias method, voxel sampling becomes a viable alternative to sampling space with the 0(1) approach of uniformly sampling the problem volume. Additionally, with voxel sampling it is straightforward to introduce biasing of volumetric sources, and we implement this biasing of voxels as an additional variance reduction technique that can be applied. We verify our implementation and compare the alias method, with and without biasing, to direct discrete sampling of voxels, and to uniform sampling. We study the behavior of source biasing in a second set of tests and find trends between improvements and source shape, material, and material density. Overall, however, the magnitude of improvements from source biasing appears to be limited. Future work will benefit from the implementation of efficient voxel sampling - particularly with conformai unstructured meshes where the uniform sampling approach cannot be applied.
KW - Activation
KW - Alias method
KW - Monte Carlo
KW - R2S
KW - Source biasing
UR - http://www.scopus.com/inward/record.url?scp=84883427140&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84883427140
SN - 9781627486439
T3 - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
SP - 938
EP - 949
BT - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
T2 - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
Y2 - 5 May 2013 through 9 May 2013
ER -