Neutron sources for BNCT using low-power Research reactors or compact charged particle accelerators

Proceedings of SPIE - The International Society for Optical Engineering

Volumn 2867, Issue , 1996, Pages 48-54

  Harker, Yale D ^a   Nigg, David W ^a   Mitchell, Hannah E ^a   Wheeler, Floyd J ^a   Jones, James L ^a  

^a IDAHO NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCELERATION; CHARGED PARTICLES; INDUSTRIAL RESEARCH; LABORATORIES; NEUTRON BEAMS; NEUTRON SOURCES; PARTICLE ACCELERATORS; PLASMA ACCELERATORS; RESEARCH REACTORS;

BROOKHAVEN NATIONAL LABORATORY; CONCEPTUAL DEVELOPMENT; EPITHERMAL NEUTRON BEAMS; EPITHERMAL NEUTRON SOURCE; FILTER MATERIALS; IDAHO NATIONAL ENGINEERING LABORATORY; MEDICAL RESEARCH; THRESHOLD ENERGY;

NEUTRONS;

EID: 0344367324     PISSN: 0277786X     EISSN: 1996756X     Source Type: Conference Proceeding    
DOI: 10.1117/12.267933     Document Type: Conference Paper

References (7)

1. Auterinen and P. Hiismaki, "Epithermal BNCT Neutron Beam Design for a TRIGA II Reactor", Advances in Neutron Capture Therapy, R. Barth and A. Soloway, Editors, Plenum Press, New York, 1993, pp 81-84.
2. Jones and W. Y. Yoon, "Feasibility Study of the Application of a Linear Electron Accelerator to BNCT", Proceedings of the 12th International Conference on the Application of Accelerators in Research and Industry, University of North Texas, Denton TX, November, 1992.
3. Wang, et. al., "A Neutronic Study of an Accelerator-Based Neutron Irradiation Facility for Boron Neutron Capture Therapy", Nuclear Technology, 84:93 (1989)
4. Hablieb and T. A. Mehlhorn, "ITS - The Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes", SAND84-05873, Sandia National Laboratory, November, 1984.
5. Jones, et. al, "Material Identification Technology (MIT) - Concept Feasibility Study", WINCO-1147, Idaho National Engineering Laboratory (1993).
6. Rhoades and R. L. Childs, "An Updated Version of the DOT-4 One- and Two-Dimensional Neutron/Photon Transport Code, ORNL-5851, Oak Ridge National Laboratory (1982).
7. Briesmeister, editor, "MCNP - A General Monte Carlo Code for Neutron and Photon Transport", LA-7396 (Rev 2), Los Alamos National Laboratory, September 1986.