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Epithermal beam development at the BMRR (Brookhaven Medical Research Reactor) [electronic resource] : Dosimetric evaluation

Published
Washington, D.C : United States. Dept. of Energy. Office of Energy Research, 1989.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: (11 pages) : digital, PDF file
Additional Creators
Brookhaven National Laboratory, United States. Department of Energy. Office of Energy Research, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The utilization of an epithermal neutron beam for neutron capture therapy (NCT) is desirable because of the increased tissue penetration relative to a thermal neutron beam. Over the past few years, modifications have been and continue to be made at the Brookhaven Medical Research Reactor (BMRR) by changing its filter components to produce an optimal epithermal beam. An optimal epithermal beam should contain a low fast neutron contamination and no thermal neutrons in the incident beam. Recently a new moderator for the epithermal beam has been installed at the epithermal port of the BMRR and has accomplished this task. This new moderator is a combination of alumina (Al₂O₃) bricks and aluminum (Al) plates. A 0.51 mm thick cadmium (Cd) sheet has reduced the thermal neutron intensity drastically. Furthermore, an 11.5 cm thick bismuth (Bi) plate installed at the port surface has reduced the gamma dose component to negligible levels. Foil activation techniques have been employed by using bare gold and cadmium-covered gold foil to determine thermal as well as epithermal neutron fluence. Fast neutron fluence has been determined by indium foil counting. Fast neutron and gamma dose in soft tissue, free in air, is being determined by the paired ionization chamber technique, using tissue equivalent (TE) and graphite chambers. Thermoluminescent dosimeters (TLD-700) have also been used to determine the gamma dose independently. This paper describes the methods involved in the measurements of the above mentioned parameters. Formulations have been developed and the various corrections involved have been detailed. 12 refs.
Report Numbers
E 1.99:bnl-43271
E 1.99: conf-8903150--4
conf-8903150--4
bnl-43271
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Other Subject(s)
Note
Published through SciTech Connect.
08/24/1989.
"bnl-43271"
" conf-8903150--4"
"DE90001272"
Workshop on neutron beam design, development and performance for neutron capture therapy, Cambridge, MA (USA), 30-31 Mar 1989.
Ramsey, E.; Fairchild, R.G.; Laster, B.H.; Saraf, S.K.; Kalef-Ezra, J.; Fiarman, S.; State Univ. of New York, Stony Brook, NY; Brookhaven National Lab., Upton, NY; Ioannina Univ.
Funding Information
AC02-76CH00016
View MARC record | catkey: 14794908