Abstract
In this paper a novel deterministic calculation method of
three-dimensional neutron transport is presented, based
on the tree-multigrid (TMG) technique and SP3
approximation. The neutron fluence rate distribution has
been calculated for cylindrical PMMA
(polymethyl-methacrylate) phantom used in
characterisation of Finnish epithermal beam. The PMMA
phantom and neighbouring beam collimator structures have
been modelled by a CAD system. An octree grid of the
advanced tree-multigrid iteration technique has been
generated directly from CAD files. The source plane
fluence used in Monte Carlo based treatment planning has
been utilised. Calculations have been carried out with
47-group BUGLE cross sections. The applicability of the
method in BNCT dose planning is discussed.
| Original language | English |
|---|---|
| Title of host publication | Proceedings of the ninth international symposium on neutron capture therapy for cancer |
| Place of Publication | Osaka |
| Pages | 137 - 138 |
| Publication status | Published - 2000 |
| MoE publication type | A4 Article in a conference publication |
| Event | 9th International Symposium on Neutron Capture Therapy for Cancer: NCT Osaka 2000 - Osaka, Japan Duration: 2 Oct 2000 → 6 Oct 2000 |
Conference
| Conference | 9th International Symposium on Neutron Capture Therapy for Cancer |
|---|---|
| Country/Territory | Japan |
| City | Osaka |
| Period | 2/10/00 → 6/10/00 |