Moderator material for neutrons and use of said material

Details Moderator material for neutrons and use of said material Moderator material for neutrons and use of said material

G - Physics

21

K

G21K 1/00 (2006.01) A61N 5/10 (2006.01) G21C 5/00 (2006.01) G21C 5/12 (2006.01) G21K 5/04 (2006.01) H05H 3/06 (2006.01)

Patent

CA 2165300

The invention concerns a moderator material used for moderation of high-velocity neutrons, in particular of fission neutrons, to epithermal neutrons. The principal components of the moderator material are aluminum fluoride and aluminum metal, which have been formed into a dense composite free of pores, wherein the material contains 20...50 %-vol. of aluminum metal and 80...50 %-vol. of aluminum fluoride. Further, the use of the moderator material in accordance with the invention in neutron capture therapy of cancer tumours is described, such as in boron neutron capture therapy (BNCT).

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