TY - JOUR
T1 - Measurement of thermal neutron fluence distribution with use of 23Na radioactivation around a medical compact cyclotron
AU - Fujibuchi, Toshioh
AU - Yamaguchi, Ichiro
AU - Kasahara, Tetsuharu
AU - Iimori, Takashi
AU - Masuda, Yoshitada
AU - Kimura, Ken Ichi
AU - Watanabe, Hiroshi
AU - Isobe, Tomonori
AU - Sakae, Takeji
PY - 2009/7
Y1 - 2009/7
N2 - A medical compact cyclotron produces about 1015 neutrons per day along with 100 GBq of 18F. Therefore, it is important to establish radiation safety guidelines on residual radioactivity for routine operation, maintenance work, and decommissioning. Thus, we developed a simple method for measuring the thermal neutrons in a cyclotron room. In order to verify the feasibility of our proposed method, we measured the thermal neutron distribution around a cyclotron by using the activation of 23Na in salt. We installed 78 salt dosimeters in the cyclotron room with a 50 cm mesh. The photopeak of 24Na was measured, and the neutron flux distribution was estimated. Monitoring the neutron flux distribution in a cyclotron room appears to be useful for not only obtaining an accurate estimate of the distribution of induced radioactivity, but also optimizing the shield design for radiation safety in preparation for the decommissioning process.
AB - A medical compact cyclotron produces about 1015 neutrons per day along with 100 GBq of 18F. Therefore, it is important to establish radiation safety guidelines on residual radioactivity for routine operation, maintenance work, and decommissioning. Thus, we developed a simple method for measuring the thermal neutrons in a cyclotron room. In order to verify the feasibility of our proposed method, we measured the thermal neutron distribution around a cyclotron by using the activation of 23Na in salt. We installed 78 salt dosimeters in the cyclotron room with a 50 cm mesh. The photopeak of 24Na was measured, and the neutron flux distribution was estimated. Monitoring the neutron flux distribution in a cyclotron room appears to be useful for not only obtaining an accurate estimate of the distribution of induced radioactivity, but also optimizing the shield design for radiation safety in preparation for the decommissioning process.
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U2 - 10.1007/s12194-009-0060-7
DO - 10.1007/s12194-009-0060-7
M3 - Article
C2 - 20821115
AN - SCOPUS:68449093104
SN - 1865-0333
VL - 2
SP - 159
EP - 165
JO - Radiological physics and technology
JF - Radiological physics and technology
IS - 2
ER -