Physics Parameters for an Epithermal—Neutron Beam at the Georgia Institute of Technology

  • David W. Nigg
  • Gregory J. Storr
  • Floyd J. Wheeler


Boron Neutron Capture Therapy (BNCT) research in the United States has focused on the use of epithermal (0.5 eV to 10 key) neutron beams for treatment of certain highly-malignant primary brain tumors and possibly for treatment of metastatic malignant melanoma. Various types of epithermal neutron sources for BNCT have been proposed over the years. Reactor-based sources, accelerator-based sources, and radioactive neutron sources have all been extensively examined. The first practical, large-scale, epithermal neutron beam for BNCT was installed at the Brookhaven Medical Research Reactor (BMRR)1. This beam was designed and constructed in a cooperative effort between Brookhaven National Laboratory (BNL) and the Idaho National Engineering Laboratory (INEL). It has been used extensively for BNCT research activities conducted by INEL, BNL, and others.


Neutron Beam Boron Neutron Capture Therapy Relative Biological Effectiveness Epithermal Neutron Brookhaven National Laboratory 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.


Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.


  1. 1.
    F.J. Wheeler,, Epithermal neutron beam design for neutron capture therapy at the power burst facility and the Brookhaven Medical Research Reactor, Nuclear Technology 92, 106, October, 1990.Google Scholar
  2. 2.
    W.A. Rhoades, and R.L. Childs, An updated version of the DOT-4 one-and two-dimensional neutron/photon transport code, Oak Ridge National Laboratory, ORNL-5851, April 1982.Google Scholar
  3. 3.
    W.A. Rhoades, and R.L. Childs, The TORT three-dimensional discrete-ordinates neutron/photon transport code, Oak Ridge National Laboratory, ORNL-6268, 1987.Google Scholar
  4. 4.
    R.W. Roussin, BUGLE-80 coupled 47-neutron, 20 gamma-ray P3 cross section library, Radiation Shielding Information Center, DLC-75, 1980.Google Scholar
  5. 5.
    MCNP Monte Carlo neutron and photon transport code systems, Radiation Shielding Information Center, CC-200A.Google Scholar
  6. 6.
    G.S. Robinson, A guide to the AUS modular neutronics code system, AAEC/E645, (Australian Atomic Energy Commission), April 1987.Google Scholar
  7. 7.
    D.W. Nigg,, Demonstration of three-dimensiona deterministic radiation transport theory dose distribution analysis for Boron Neutron Capture Therapy, Medical Physics 18:1, 43–53, January 1991.PubMedCrossRefGoogle Scholar
  8. 8.
    F.J. Wheeler and D.W. Nigg, Three-dimensional radiation dose distribution analysis for neutron capture therapy, Nuclear Scienceand Engineering,110, 16–31, January 1992.Google Scholar
  9. 9.
    P.R. Gavin, et. al., Large animal model - the biologic effects of mixed irradiation fields utilizing BSH and epithermal neutron irradiation, Proceedings of International Workshop on Macro-and Microdosimetry and Treatment Planning for Neutron Capture Therapy, MIT, October 1991, (To be published).Google Scholar

Copyright information

© Springer Science+Business Media New York 1993

Authors and Affiliations

  • David W. Nigg
    • 1
  • Gregory J. Storr
    • 1
  • Floyd J. Wheeler
    • 1
  1. 1.National Center for BNCT Measurement and Development Idaho National Engineering LaboratoryEG&G Idaho, Inc.Idaho FallsUSA

Personalised recommendations