Effective dose evaluation for BNCT treatment in the epithermal neutron beam at THOR

Applied Radiation and Isotopes - Tập 69 - Trang 1850-1853 - 2011
J.N. Wang1,2, C.K. Huang3, W.C. Tsai1, Y.H. Liu4, S.H. Jiang1,3
1Department of Engineering and System Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan
2Division of Health Physics, Institute of Nuclear Energy Research, No. 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan
3Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan
4Nuclear Science and Technol. Develop. Center, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan

Tài liệu tham khảo

Eckerman, K.F., Chisty, M., Ryman, J.C., 1996. The ORNL Mathematical Phantom Series. Available from: 〈http://ats.ornl.gov/documents/mird2.pdf〉. ICRP, 1991 ICRP, 2003 ICRP, 2007 ICRU, 1992 Kotiluoto, P., Auterinen, I., Savolainen, S., 2006. Effective Whole Body Dose in Epithermal Neutron Irradiation at the FiR 1 BNCT facility. ICNCT-12, Takamatsu, Kagawa, Japan, October 9–13. Lee, 2005, Effective dose evaluation for chest and abdomen X-ray tests, Radiat. Prot. Dosimetry, 116, 613, 10.1093/rpd/nci007 Matsumoto, T., Uchiyama, T., 2002. Calculation of whole-body organic dose in brain tumor treatment by boron neutron capture therapy. Research and Development in Neutron Capture Therapy, Essen, Germany, September 8–13. Tapiovaara, M., Siiskonen, T., 2008. PCXMC: A Monte Carlo Program for Calculating Patient Doses in Medical X-ray Examinations, 2nd Ed., STUK-A231. X-5 Monte Carlo Team, 2003. MCNP—A General Monte Carlo N-Particle Transport Code, version 5, LA-UR-03-1987. Los Alamos National Laboratory.
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Applied Radiation and Isotopes

Tập 69

1850-1853

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