TY - JOUR
T1 - Optimal radiation shielding for beta and bremsstrahlung radiation emitted by 89Sr and 90Y
T2 - Validation by empirical approach and Monte Carlo simulations
AU - Murata, Taisuke
AU - Miwa, Kenta
AU - Matsubayashi, Fumiyasu
AU - Wagatsuma, Kei
AU - Akimoto, Kenta
AU - Fujibuchi, Toshioh
AU - Miyaji, Noriaki
AU - Takiguchi, Tomohiro
AU - Sasaki, Masayuki
AU - Koizumi, Mitsuru
N1 - Funding Information:
Acknowledgments The authors thank the staff of the Department of Radiology and Nuclear medicine at Cancer Institute Hospital of Japanese Foundation for Cancer Research (JFCR) for providing valuable clinical support. This study was supported in part by a Grant-in-Aid from the Clinical Research Center at the Cancer Institute Hospital of JFCR.
Copyright:
Copyright 2014 Elsevier B.V., All rights reserved.
PY - 2014/8
Y1 - 2014/8
N2 - Objective: High-energy beta emitters such as Strontium-89 (89Sr) and Yttrium-90 (90Y) are becoming increasingly popular nuclear therapy sources in Japan for treating cancer. Various characteristics of materials must be considered when designing radiation protection device for high-energy beta emitters. We empirically measured and simulated dose equivalents of beta and bremsstrahlung radiation arising from 89Sr and 90Y radiation shielded with various materials and determined optimal shielding materials against these sources. Methods: The dose equivalents of 89Sr and 90Y determined experimentally using an ionization chamber survey meter were compared with those of Monte Carlo simulations. The relative dose equivalents of beta and bremsstrahlung radiation separately transmitted by changing the thickness of acrylic, aluminum, iron, lead and tungsten shielding materials were simulated. Results: Dose equivalents were consistent between the empirical measurements and the simulation to within ±5 %. Shielding ability was more effective in the order of tungsten, lead, iron, aluminum and acrylic against both 89Sr and 90Y. The amount of beta and bremsstrahlung radiation transmitted through tungsten and lead was relatively small. Although such high-density material generates much bremsstrahlung radiation, it absorbs the bremsstrahlung radiations. Conclusions: Tungsten was the optimal material for efficient shielding against 89Sr and 90Y radiation and preferable among operators. The present findings provide useful information about how to define an appropriate shielding strategy for high-energy beta emitters.
AB - Objective: High-energy beta emitters such as Strontium-89 (89Sr) and Yttrium-90 (90Y) are becoming increasingly popular nuclear therapy sources in Japan for treating cancer. Various characteristics of materials must be considered when designing radiation protection device for high-energy beta emitters. We empirically measured and simulated dose equivalents of beta and bremsstrahlung radiation arising from 89Sr and 90Y radiation shielded with various materials and determined optimal shielding materials against these sources. Methods: The dose equivalents of 89Sr and 90Y determined experimentally using an ionization chamber survey meter were compared with those of Monte Carlo simulations. The relative dose equivalents of beta and bremsstrahlung radiation separately transmitted by changing the thickness of acrylic, aluminum, iron, lead and tungsten shielding materials were simulated. Results: Dose equivalents were consistent between the empirical measurements and the simulation to within ±5 %. Shielding ability was more effective in the order of tungsten, lead, iron, aluminum and acrylic against both 89Sr and 90Y. The amount of beta and bremsstrahlung radiation transmitted through tungsten and lead was relatively small. Although such high-density material generates much bremsstrahlung radiation, it absorbs the bremsstrahlung radiations. Conclusions: Tungsten was the optimal material for efficient shielding against 89Sr and 90Y radiation and preferable among operators. The present findings provide useful information about how to define an appropriate shielding strategy for high-energy beta emitters.
UR - http://www.scopus.com/inward/record.url?scp=84906331436&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84906331436&partnerID=8YFLogxK
U2 - 10.1007/s12149-014-0853-6
DO - 10.1007/s12149-014-0853-6
M3 - Article
C2 - 24816948
AN - SCOPUS:84906331436
SN - 0914-7187
VL - 28
SP - 617
EP - 622
JO - Annals of Nuclear Medicine
JF - Annals of Nuclear Medicine
IS - 7
ER -