Abstract
A collaborative effort by researchers at the Idaho National Engineering Laboratory and the Brookhaven National Laboratory has resulted in the design and implementation of an epithermal-neutron source at the Brookhaven Medical Research Reactor (BMRR). Large aluminum containers, filled with aluminum oxide tiles and aluminum spacers, were tailored to pre-existing compartments on the animal side of the reactor facility. A layer of cadmium was used to minimize the thermal-neutron component. Additional bismuth was added to the pre-existing bismuth shield to minimize the gamma component of the beam. Lead was also added to reduce gamma streaming around the bismuth. The physics design methods are outlined in this paper. Information available to date shows close agreement between calculated and measured beam parameters. The neutron spectrum is predominantly in the intermediate energy range (0.5 eV – 10 keV). The peak flux intensity is 6.4E+12 n/(m2·s·MW) at the center of the beam on the outer surface of the final gamma shield. The corresponding neutron current is 3.8E+12 n/(m2·s·MW). Presently, the core operates at a maximum of 3 MW. The fast-neutron KERMA is 3.6E−15 cGy/(n/m2) and the gamma KERMA is 5.0E−16 cGy/(n/m2) for the unperturbed beam. The neutron intensity falls off rapidly with distance from the outer shield and the thermal flux realized in phantom or tissue is strongly dependent on the beam-delimiter and target geometry.
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References
W. A. Neuman, “Neutron Beam Studies for a Medical Therapy Reactor.” (These Proceedings.)
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).
Proc. Second Int. Symp. on Neutron Capture Therapy, Tokyo, 1985, H. Hatanaka, ed., Nishimura Co., Ltd., Niigata, Japan (1986).
R. G. Fairchild, “Development and Dosimetry of an ‘Epithermal’ Neutron Beam for Possible Use in Neutron Capture Therapy,” Phys. Med. Biol., 10 (4): 491 (1965).
J. B. Godel, “Description of Facilities and Mechanical Components, Medical Research Reactor (MRR),” Brookhaven National Laboratory, BNL-600 (T-1731 (1960).
R. G. Fairchild, Personal Communication.
G. E. Putnam, TOPIC-A FORTRAN Program for the Calculation of Transport of Particles in Cylinders,“ Idaho National Engineering Laboratory, IDO-16968 (1964). (SCAMP is a multigroup version of the TOPIC Program.)
R. A. Grimesey and R. L. Curtis, “COMBINE: Combined Fast and Thermal B-3 Spectrum Code to Produce Fast and Thermal Multigroup Neutron Cross Sections.” (To be Published.)
R. G. Fairchild, J. Kalef-Ezra, S. Fiarman, I. Wielopolski, J. Hanz, S. Mussolino, and F. Wheeler, “Optimization on an Epithermal Neutron Beam for NCT at the Brookhaven Medical Research Reactor (BMRR),” Strahlenther. Onkol., 165 (2/3): 84 (1989).
Y. Oka, I. Yanagisawa, and S. An, “A Design Study of the Neutron Irradiation Facility for Boron Neutron Capture Therapy,” Nucl. Technol., 55 (3): 642 (1981).
R. M. Brugger, T. J. Less, and G. G. Passmore, “An Intermediate-Energy Neutron Beam for NCT at MURR,” in 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, p. 83 (1987).
W. A. Rhoades and R L Childs, “Updated Version of the DOT 4 One-and Two-Dimensional Neutron/Photon Transport Code,” Oak Ridge National Laboratory, ORNL-5851 (1982).
R. W. Roussin, “BUGLE-80: Coupled 47-Neutron, 20-Gamma-Ray, P3, Cross-Section Library for LWR Shielding Calculations,” Radiation Shielding Information Center, DLC-75 (1980).
D. K. Parsons, F. J. Wheeler, B. I. Rushton, and D. W. Nigg, “Neutronics Design of the INEL Facility for Boron Neutron Capture Therapy Clinical Trials,” in Proc. ANS 1988 Int. Reactor Physics Conf., Jackson Hole, WY, Vol. II, p. 2–443 (Sept. 1988).
G. K. Becker, Y. D. Harker, R. A. Anderl, and F. J. Wheeler, “Neutron Spectrum Measurements in the Aluminum Oxide Filtered Beam Facility at the Brookhaven Medical Research Reactor.” (These Proceedings.)
M. A. Abdou, Y. Gohar, and R. Q. Wright, “MACK-IV: A New Version of MACK, A Program to Calculate Nuclear Response Functions from Data in ENDF/B Format,” Argonne National Laboratory, ANL/FPP-75–5 (July 1978).
F. J. Wheeler, “The Power Burst Reactor Facility as an Epithermal Neutron Source for Brain Cancer Therapy,” in 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, p. 92 (1987).
P. D. Randolph, Personal Communication.
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© 1990 Plenum Press, New York
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Wheeler, F.J., Parsons, D.K., Nigg, D.W., Wessol, D.E., Miller, L.G., Fairchild, R.G. (1990). Physics Design for the Brookhaven Medical Research Reactor Epithermal Neutron Source. In: Harling, O.K., Bernard, J.A., Zamenhof, R.G. (eds) Neutron Beam Design, Development, and Performance for Neutron Capture Therapy. Basic Life Sciences, vol 54. Springer, Boston, MA. https://doi.org/10.1007/978-1-4684-5802-2_7
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DOI: https://doi.org/10.1007/978-1-4684-5802-2_7
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