Conceptual Design of a Deuteron Linac Facility for Boron Neutron Capture Therapy
It has been generally accepted that the optimum neutron source for Boron Neutron Capture Therapy (BNCT) is a small or intermediate reactor. Currently available research reactors in Japan are not constructed exclusively for the medical use, but rather multi-purpose reactors. Since the thermal neutron flux available at the beam port is not so high, the time required for the treatment is usually rather long. Further, the time available for the medical use is limited because the research reactors are used for different purposes. Studies of BNCT by epithermal neutrons are in progress in U.S.A., Europe and Australia. If epithermal neutrons are utilized, it may be possible to treat deep-seated cancers without surgery.
KeywordsNeutron Flux Thermal Neutron Fast Neutron Heavy Water Neutron Yield
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- 1.J. Hirota, et al.,Design Study of a Deuteron Linac Facility for Boron Neutron Capture Therapy, Proc. First Int. Workshop on Accelerator-Based Neutron Sources for Boron Neutron Capture Therapy, Sept. 11–14, 1994, Jackson, U.S.A..Google Scholar
- 2.M. Sasaki, et al.,Progress in Study of a Medical Reactor for Boron Neutron Capture Therapy, P-510, Fifth Int. Sympo. on Advanced Nuclear Energy Research, March 10–12, 1993, Mito, Japan.Google Scholar
- 3.K. Kanda and Y. Mishima, J. At. Energy Soc. Japan, 35: 371–372, 1993 (in Japanese).Google Scholar
- 4.P. Grand, et al.,Nucl. Tech., 29: 327–336, 1976.Google Scholar
- 5.Y. Oka et al.,ibid., 55: 642–655, 1981.Google Scholar
- 6.A. Hasegawa,Development of a Common Neutron Group Constants Library System;JSSTDL-295n- 104)’ Based on JENDL-3 Nuclear Library, Proc. Int. Conf. Nucl. Data for Sci. and Tech., May 13–17, 1991, Julich, FRG.Google Scholar
- 8.Protection against Neutron Radiation, Jan. 4, 1971, National Council on Radiation and Measurement (NCRP).Google Scholar
- 9.IC RP Publication 21, Table 4,1973.Google Scholar