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Tomita, Jumpei; Takeuchi, Erina
Applied Radiation and Isotopes, 150, p.103 - 109, 2019/08
Times Cited Count:14 Percentile:84.04(Chemistry, Inorganic & Nuclear)A rapid analytical method for determining Sr in urine samples (1-2 L) was developed to assess the internal exposure of workers in a radiological emergency. Strontium in a urine sample was rapidly separated by phosphate co-precipitation, followed by extraction chromatography with a tandem column of Pre-filter, TRU and Sr resin, and the Sr activity was determined by ICP-MS/MS. Measurement in the MS/MS mode with an O reaction gas flow rate 1 mL min showed no tailing of Sr at m/z = 90 up to 50 mg-Sr L. The interferences of Ge, Se and Zr at m/z = 90 were successfully removed by chemical separation. This analytical method was validated by the results of the analyses of synthetic urine samples (1.2-1.6 L) containing a known amount of Sr along with 1 mg of each of Ge, Se, Sr and Zr. The turnaround time for analysis was about 10 h, and the detection limit of Sr was approximately 1 Bq per urine sample.
Manabe, Kentaro; Sato, Kaoru; Takahashi, Fumiaki
BIO Web of Conferences (Internet), 14, p.03011_1 - 03011_2, 2019/05
Times Cited Count:0 Percentile:0.21(Public, Environmental & Occupational Health)Dose coefficients, which are committed effective dose per unit intake of radionuclides, are fundamental amounts for dose estimation and protection standards against internal exposures. In this study, we built a calculation function of dose coefficients using the latest dosimetric models and data as a part of development of internal dosimetry code in accordance with 2007 Recommendations of the International Commission of Radiological Protection (ICRP). Quality of the function was assured by comparing the results generated by the function to values recorded in a database of dose coefficients for workers provided by ICRP. In the presentation, we will report the results of quality assurance and the future plans of code development.
Yamamoto, Katsumune
Proceedings of 15th Sino-Japanese Seminar on Nuclear Safety, p.267 - 278, 2000/12
no abstracts in English
Tsujimura, Norio; Shinohara, Kunihiko; Momose, Takumaro
PNC TN8410 98-083, 20 Pages, 1998/05
None
Tanaka, Yoji*; Nakasawa, Otohiko*; Sugumoto, Hiroshi*; Takeshita, Hiroshi*
PNC TJ8224 92-002, 33 Pages, 1992/03
no abstracts in English
Tanaka, Yoji*; Nakasawa, Otohiko*; Sugumoto, Hiroshi*; Takeshita, Hiroshi*
PNC TJ8224 92-001, 108 Pages, 1992/03
no abstracts in English
Higuma, Takanobu; Ishida, Junichiro; ; ;
PNC TN9440 91-011, 36 Pages, 1991/08
HEALTH AND SAFETY DIVISION CONSISTS OF TWO SECTIONS,WHICH ARE SAFETYADMINISTRATION SECTION AND RADIATION CONTROL SECTION. THEIR MAIN ACTIVITIES ARE ASFOLLOWS;,ADMINISTRATION AND GUIDE OF SAFETY,RADIATION CONTROL OF NUCLEAR FACILITIES,PERSONNEL MONITORING,ENVIRONMENTA;MONITORING AND,RESEARCH AND DEVELOPMENT OF RADIATION PROTECTION TECHNOLOGY.THIS REPORT SUMMARIZES THE ABOVE ACTIVITIES OF HEALTH AND SAFETY DIVISION INO-ARAI ENGINEERING CENTER.
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Radiation Protection Dosimetry, 36(2-4), p.269 - 273, 1991/00
no abstracts in English
Tsujimura, Norio; Yoshida, Tadayoshi; Hoshi, Katsuya
no journal, ,
no abstracts in English
Tsujimura, Norio
no journal, ,
The UNSCEAR expressed concern in its 2020 report that eye lens dose due to beta particles emitted from airborne radioiodine has not been adequately assessed for the workers during the initial emergency operations after the TEPCO Fukushima Daiichi NPP accident. To address this concern, the author calculated beta Hp(3) and gamma Hp(10) delivered from radioiodine uniformly distributed in the air using the Monte Carlo particle transport code MCNP5, tabulating the conversion factors which relate the air concentration of radioiodines (Bq/cm) to the relevant dose rate (Sv/s). The radionuclides to be calculated are I-131, Te-132, I-132, and I-133. The assumed exposure conditions are (i) the concentration ratio of airborne radioiodine was I-131: Te-132 (I-132): I-133 = 1: 2.3 :1.1 at noon on March 12, (ii) I-131 equivalent to the effective dose of 100 mSv was acutely inhaled on the same day, and (iii) no respirator masks were used. Under this exposure scenario, the beta Hp(3) calculated based on the radioiodine concentrations was below 0.1 mSv regardless of indoor or outdoor exposure, which was pretty smaller than the recorded gamma Hp(10).