Abstract
Computational studies are performed for choosing an optimal material and dimensions of a moderator for forming a beam of epithermal neutrons for boron-neutron-capture therapy based on a proton accelerator and the reaction 7 Li(p, n)7 Be as the neutron source. It is shown that the best material for this is magnesium fluoride. An optimal configuration is proposed for a combined moderator consisting of magnesium fluoride and teflon. The computational results are compared with the experimental data.
Similar content being viewed by others
REFERENCES
R. Moss O. Aiazawa D. Beynon et al. (1997) ArticleTitleThe requirements and development of neutron beams for neutron capture therapy of brain cancer Neuro-Oncology 33 27–40
O. Harling K. Riley T. Newton et al. (2002) ArticleTitleThe fission converter-based epithermal neutron irradiation facility at the Massachusetts Institute of Technology reactor Nucl. Sci. Eng. 140 223–240
O. Harling and K. Riley, “A critical assessment of NCT beams for fission reactors,” in: Proceedings of the 10th International Congress on Research and Development in Neutron Capture Therapy, Essen, Germany (2002), pp. 159–162.
P. Binns, K. Riley, and O. Harling, “Dosimetric comparison of six epithermal neutron beams using an ellipsoidal water phantom,” ibid., pp. 405–409.
C.-K. Wang T. Blue R. Gahbauer (1989) ArticleTitleA neutronic study of an accelerator-based neutron irradiation facility for boron neutron capture therapy Nucl. Tech. 84 93–107
A. Allen T. Beynon (1995) ArticleTitleA design study for an accelerator based epithermal neutron beam for BNCT Phys. Med. Biol 40 807–821
D. Bluel R. Donahue B. Ludewigt et al. (1998) ArticleTitleDesigning accelerator-based epithermal neutron beams for boron neutron capture therapy Med. Phys 25 1725–1734
B. Bayanov M. Bokhovko V. Kononov et al. (1998) ArticleTitleAccelerator-based neutron source for the neutron capture and fast neutron therapy at hospital Nucl. Instrum. Methods in Phys. Res. A 413 397–426
V. N. Kononov E. D. Poletaev B. D. Yurlov (1977) ArticleTitleAbsolute yield and spectrum of neutrons from the reaction 7Li(p, n)7Be At. Énerg 43 IssueID4 303–305
O. E. Kononov, V. N. Kononov, and M. V. Bokhovko, “Accelerator-based neutron sources for neutron and neutron-capture therapy,” Preprint FÉI-2985 (2003).
A. K. Zhitnik, “Monte Carlo method at the All-Russia Scientific-Research Institute of Experimental Physics,” Vopr. At. Nauk. Tekh., Ser. Mat. Modelir. Fiz. Prots., No. 2, 61–64 (1993).
J. Briesmeister, MCNP-A General Monte Carlo n-Particle Transportation Code, LA-1625-M, Ver. 4B (1997).
O. E. Kononov, V. N. Kononov, V. V. Korobeinikov, et al., “Optimization of an epithermal-neutron source based on the reaction 7Li(p, n)7Be for neutron-capture therapy,” Preprint FÉI-2984(2003).
O. E. Kononov V. N. Kononov N. A. Solov’ev (2003) ArticleTitleNeutron source for boron-neutron capture therapy based on the reaction 7Li(p, n)7Be near threshold At. Énerg 94 IssueID6 469–472
Author information
Authors and Affiliations
Additional information
Translated from Atomnaya Énergiya, Vol. 97, No. 3, pp. 195–200, September, 2004.
Rights and permissions
About this article
Cite this article
Kononov, O.E., Kononov, V.N., Solov’ev, A.N. et al. Accelerator-based source of epithermal neutrons for neutron capture therapy. At Energy 97, 626–631 (2004). https://doi.org/10.1007/s10512-005-0043-7
Received:
Issue Date:
DOI: https://doi.org/10.1007/s10512-005-0043-7