Intermediate Energy Neutron Beams from the MURR
Several reactors in the United States are potential candidates to deliver beams of intermediate energy neutrons for NCT. At this time, moderators, as compared to filters, appear to be the more effective means of tailoring the flux of these reactors. The objective is to sufficiently reduce the flux of fast neutrons while producing enough intermediate energy neutrons for treatments. At the University of Missouri Research Reactor (MURK), the code MCNP has recently been used to calculate doses in a phantom. First, “ideal” beams of 1, 35, and 1000 eV neutrons were analyzed to determine doses and advantage depths in the phantom. Second, a high quality beam that had been designed to fit in the thermal column of the MURR, was reanalyzed. MCNP calculations of the dose in phantom in this beam confirmed previous calculations and showed that this beam would be a nearly ideal one with neutrons of the desired energy and also a high neutron current. However, installation of this beam will require a significant modification of the thermal column of the MURR. Therefore, a second beam that is less difficult to build and install, but of lower neutron current, has been designed to fit in MURR port F. This beam is designed using inexpensive Al, S, and Pb. The doses calculated in the phantom placed in this beam show that it will be satisfactory for sample tests, animal tests, and possible initial patient trials. Producing this beam will require only modest modifications of the existing tube.
KeywordsFast Neutron Neutron Dose High Quality Beam Code MCNP Ideal Beam
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- 1.Proc_. First Int. Symp. on Neutron Capture Therapy, Cambridge, MA, 1983, R. G. Fairchild and G. L. Brownell, eds., Brookhaven National Laboratory, BNL-51730 (1984).Google Scholar
- 2.Proc. Second Int. Symp. on Neutron Capture Therapy, Tokyo, 1985, H. Hatanaka, ed., Nishimura Co., Ltd., Niigata, Japan (1986).Google Scholar
- 3.Proc. U.S. Dept. of Energy 1986 Workshop on Neutron Capture Therapy, R. G. Fairchild and V. P. Bond, eds., Brookhaven National Laboratory, BNL-51994 (1987).Google Scholar
- 4.Proc. Third Int. Symp. on Neutron Capture Therapy, Strahlenther. Onkol., D. Gabel, ed., 165(2/3):5–257 (1989).Google Scholar
- 5.Nuclear Reactors Built, Being Built, or Planned in the United States,“ National Technical Information Service, U.S. Department of Commerce, PB82–903002.Google Scholar
- 6.T. J. Less and R. M. Brugger, “Reactor Moderated Intermediate Energy Neutron Beams for Neutron Capture Therapy,” Strahlenther. Onkol., 165(2/3):87 (1989).Google Scholar
- 7.T. J. Less, “Reactor Moderated Intermediate Energy Neutron Beams for Neutron Capture Therapy,” Ph.D. Dissertation, Nuclear Engineering Department, University of Missouri-Columbia, Columbia, MO (1987).Google Scholar