Non-reactor neutron sources for BNCT (Boron Neutron Capture Therapy)

Technical Report · Mon May 01 04:00:00 EDT 1989

DOI:https://doi.org/10.2172/5876401· OSTI ID:5876401

Dolan, T. J.; Ottewitte, E. H.; Wills, E. E.; Neuman, W. A.; Woodall, D. M.

The focus of this study is the indentification of key feasibility issues for the use of non-reactor neutron sources for Boron Neutron Capture Therapy (BNCT). Of the non-reactor neutron sources surveyed, the /sup 7/Li(p,n) reaction appears to be the most favorable for producing epithermal neutrons for BNCT, and RFQ accelerators are best for producing the desired proton beam. At a proton energy of 2.5 MeV, the total neutron yield is 1.49 /times/ 10/sup /minus/4/ neutrons/proton, with a forward energy spectrum extending up to 780 keV and peaked at 500-600 keV. At I = 20 mA, the total neutron yield would be about 1.86 /times/ 10/sup 13/ neutrons/s. In comparison with a medical therapy fission reactor, the 20 mA accelerator system has a flux intensity at least 5 times lower, requiring an irradiation time at least 5 times longer, a much higher gamma intensity, which would probably require additional shielding, further reducing the neutron intensity, 30% of the neutrons above 15 keV, resulting in a higher fast neutron dose to healthy tissue, poorer spatial uniformity of the neutron beam, and greater angular divergence of the neutron beam, resulting in a rapid decrease of flux with distance from the filter. The possibility of overcoming these limitations by using more shielding and a higher beam current needs further study. RFQ accelerator technology is being developed to provide the desired proton beam parameters. The effects of neutron beam energy spectra, beam contaminants, angular divergence, spatial variation, and beam rotation around the tumor need to be studied in detail, in order to evaluate the feasibility of accelerator-produced neutrons for BNCT. 41 refs., 20 figs., 8 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5876401
• Report Number(s): EGG-BNCT-8319; ON: DE89016211
• Country of Publication: United States
• Language: English

Related Subjects

07 ISOTOPE AND RADIATION SOURCES
070201 -- Radiation Sources-- Design
Fabrication & Operation
550603* -- Medicine-- External Radiation in Therapy-- (1980-)
62 RADIOLOGY AND NUCLEAR MEDICINE
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BEAMS
BORON 10 TARGET
CHARGED-PARTICLE REACTIONS
CROSS SECTIONS
DESIGN
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
HADRON REACTIONS
IONIZING RADIATIONS
LITHIUM 7 TARGET
MEDICINE
NEUTRON BEAMS
NEUTRON CAPTURE THERAPY
NEUTRON SOURCES
NEUTRON SPECTRA
NEUTRON THERAPY
NUCLEAR MEDICINE
NUCLEAR REACTIONS
NUCLEON BEAMS
NUCLEON REACTIONS
PARTICLE BEAMS
PARTICLE SOURCES
PROTON REACTIONS
RADIATION SOURCES
RADIATIONS
RADIOLOGY
RADIOTHERAPY
SCATTERING
SPECTRA
TARGETS
THERAPY