O. Aizawa, EVALUATION OF NEUTRON-IRRADIATION FIELD FOR BORON NEUTRON-CAPTURE THERAPY BY USING ABSORBED DOSE IN A PHANTOM, International journal of radiation oncology, biology, physics, 28(5), 1994, pp. 1143-1148
Citations number
4
Categorie Soggetti
Oncology,"Radiology,Nuclear Medicine & Medical Imaging
Purpose:: The method of an evaluation for the dose characteristics of
BNCT is presented, and an eccentric core design for the TRIGA-II react
or is proposed. Methods and Materials:: We have defined the ''irradiat
ion time'' as the time of irradiation in which the ''maximum 1 mu g/g
dose'' becomes 3,000 RBE-cGy, because we assumed that the normal tissu
e contained 1 mu g/g B-10. We have also changed the RBE values and cal
culated the absorbed dose in the ''irradiation time'' by using an arra
ngement including both a facility structure and a body phantom. Moreov
er, we have modified the dose criteria for BNCT as follows: The ''eye
dose,'' ''total body dose,'' and ''except-head dose'' should be less t
han 200, 100, and 50 RBE-cGy, respectively. We have added one more cri
teria for BNCT-that the thermal neutron fluence at the tumor position
(5 cm from the surface) should be over 2.5 X 10(12) n/cm(2) in the ''i
rradiation time.'' Results:: The distance from the core side to the ir
radiation port is a very important factor to design a neutron irradiat
ion field for BNCT. Conclusion:: We can get the acceptable dose for BN
CT with only 1-h irradiation by using a 100 kW reactor if we can get t
he irradiation port at the distance of 120 cm from the core side.