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Design Considerations for the Proposed Hifar Thermal and Epithermal Neutron Capture Therapy Facilities

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Abstract

At the Australian Nuclear Science and Technology Organisation (Ansto) the 100kW reactor Moata has been used successfully for Boron Neutron Capture Therapy (BNCT) of murine melanoma xenografts.1 Envisaged large animal and human irradiations would require a beam from the High Flux Australian Reactor (HIFAR). Attaining a therapeutic beam for BNCT at HIFAR presents a challenge in physical design and engineering, as there is restricted access to core neutrons. Major modifications to the HIFAR shielding are precluded as this action would require a long shutdown and a significant and costly safety analysis. The only feasible existing beam tube that may provide a BNCT beam is the 28 cm diameter 10H re-entrant hole, located at the core mid-plane. The 10H end-plate is located approximately 9 cm from two outer core fuel elements, separated from them by D2O. The 10H facility is currently used for neutron diffraction studies, and has a collimator installed which reduces the beam to a 5 cm square hole. Figure 1 shows a vertical section of the reactor and the relative position of the 10H facility.

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References

  1. B.J. Allen, S. Corderoy-Buck, D.E. Moore, Y. Mishima, M. Ichihashi, Local control of murine melanoma xenografts in nude mice by neutron capture therapy, in these Proceedings.

    Google Scholar 

  2. B.V. Harrington, Optimisation of an Epithermal Beam in HIFAR for Boron Neutron Capture Therapy. ANSTO/E662. (1987).

    Google Scholar 

  3. W.A. Rhoades, R.L. Childs, The DORT Two-Dimensional Discrete Ordinates Transport Code, Nuclear Science and Engineering, Vol. 99, 88–89. (1988).

    Google Scholar 

  4. J.F. Briesmeister, ed. MCNP - A General Monte Carlo Code for Neutron and Photon Transport, Version 3A. LA-7396-M, Rev 2 (1986).

    Google Scholar 

  5. J.W. Connolly, A. Rose, T. Wall, Integral reaction rates and neutron energy spectra in a well moderated reactor. AAEC/TM 191. (1963).

    Google Scholar 

  6. C.H. Westcott, The Specification of Neutron Flux and Nuclear Cross-sections in Reactor Calculations. J. Nuclear Energy, Vol 2, 55–76. (1955).

    Google Scholar 

  7. B.R. Bergelson, V.P. Mashkovich, Attenuation of neutrons, in Engineering Compendium on Radiation Shielding. Vol. 1. R.G. Jaegar, E.P. Blizard, A.B. Chilton, M. Grotenhuis, A. Honig, Th. A. Jaegar and H.H Eisenlohr, eds. Springer-Verlag, New York, 497–508. (1968).

    Google Scholar 

  8. J.R. Choi, S.D. Clement, O.K. Harling, R.G. Zamenhof, Neutron Capture Therapy beams at the MIT Research Reactor in Neutron Beam Design, Development and Performance for Neutron Capture Therapy, eds., O.K. Harling, J.R. Bernard, R.G. Zamenhof, Basic Life Science Series, Vol. 54, Plenum NY, (1990).

    Google Scholar 

  9. F.J. Wheeler, The Power Burst Reactor Facility as an Epithermal Neutron Source for Brain Cancer Therapy, in Workshop on Neutron Capture Therapy, eds., R.G. Fairchild, V.P. Bond, BNL 51994 (1986).

    Google Scholar 

  10. European Collaboration. Boron Neutron Capture Therapy of Tumours. Newsletter 3. (1990).

    Google Scholar 

  11. G.S. Robinson, A Guide to the AUS Modular Neutronics Code System. AAEC/E645. (1987).

    Google Scholar 

  12. J.M. Barry, B.V. Harrington, J.P. Pollard, Aus Module POW3D - A General Purpose 0,1,2 and 3D Multigroup Diffusion Code Including Feedback-Free Kinetics. To be published.

    Google Scholar 

  13. B.V. Harrington, A Calculational Study of Tangential and Radial Beams in HIFAR for Neutron Capture Therapy, in Neutron Beam Design, Development and Performance for Neutron Capture Therapy, eds., O.K. Harling, J.R. Bernard, R.G. Zamenhof, Basic Life Science Series, Vol. 54, Plenum NY, (1990).

    Google Scholar 

  14. R.M. Brugger, A Single Crystal Silicon Thermal Neutron Filter. Nucl. Inst. Methods. 135, 289–291, (1976).

    Article  CAS  Google Scholar 

  15. B. Jacrot, Utilization of Neutron Guide Tubes for Neutron Inelastic Scattering, in Instrumentation for Neutron Inelastic Scattering Research. IAEA, Vienna. (1970).

    Google Scholar 

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© 1992 Springer Science+Business Media New York

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Storr, G.J., Allen, B.J., Harrington, B.V., Davis, L.R., Elcombe, M.M., Meriaty, H. (1992). Design Considerations for the Proposed Hifar Thermal and Epithermal Neutron Capture Therapy Facilities. In: Allen, B.J., Moore, D.E., Harrington, B.V. (eds) Progress in Neutron Capture Therapy for Cancer. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-3384-9_15

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  • DOI: https://doi.org/10.1007/978-1-4615-3384-9_15

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4613-6494-8

  • Online ISBN: 978-1-4615-3384-9

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