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Journal Articles

A Report on the 12th International Congress of the International Protection Association

Takahara, Shogo; Tsuda, Keisuke*

Hoken Butsuri, 44(1), p.9 - 12, 2009/03

This paper is a report on participation in 12th International Congress of the International Radiation Protection Association.

Journal Articles

Evaluation of the dose coefficient from ${it in vivo}$ counting to organ doses in FDG-PET

Tsuda, Keisuke; Kinase, Sakae; Fukushi, Masahiro*; Saito, Kimiaki

Hoken Butsuri, 42(4), p.349 - 352, 2007/12

no abstracts in English

Journal Articles

Evaluation of the patient internal organ doses in positron emission tomography using EGS4

Tsuda, Keisuke; Kinase, Sakae; Fukushi, Masahiro*; Saito, Kimiaki

KEK Proceedings 2006-4, p.88 - 93, 2006/11

no abstracts in English

Oral presentation

Development of evaluation method for the brain absorbed dose in $$^{18}$$F-FDG Positron Emission Tomography using voxel phantoms

Tsuda, Keisuke; Kinase, Sakae; Fukushi, Masahiro*; Saito, Kimiaki

no journal, , 

no abstracts in English

Oral presentation

Evaluation of radiation shielding ability of lead glass

Tsuda, Keisuke; Fukushi, Masahiro*; Myojoyama, Atsushi*; Kitamura, Hideaki*; Inoue, Kazumasa*; Nakaya, Giichiro*; Kimura, Junichi*; Sawaguchi, Masato*; Kinase, Sakae; Saito, Kimiaki

no journal, , 

Positron emission tomography (PET) is very effective in the diagnosis and management of patients with various types of cancers. PET scanning with the tracer FDG is widely used in clinical PET. However, the effective dose constant of the positron emitter is about eight times of nuclide $$^{99m}$$Tc used in a nuclear medicine diagnosis widely. Severe radiation protection is necessary for development of the examination with a positron emitter. Radiation protection in the PET institution therefore and safe security are problems. Hence, lead glass has attracted considerable attention as the radiation shielding materials of the PET institution. In the present study, we received a request of the radiation shielding ability evaluation of two kinds of lead glass made in Pilkington plc. The aim of the present work is the radiation shielding ability evaluation for positron emitter such as $$^{18}$$F(511 keV) of the lead glass. The shielding ability evaluation has been studied in the experimental and the Monte Carlo simulation evaluation. Consequently, effective dose transmission factor with experimental and the Monte Carlo simulation value was calculated. There were enough protection effects to evaluated lead glass. Furthermore, radiation shielding ability evaluation for $$^{137}$$Cs(662 keV), $$^{60}$$Co(1.17, 1.33 MeV) was performed, and it was shown that there was a similar protection effect.

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