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Journal Articles

40 years of TLD badge monitoring experience and operational dose quantities

Tsujimura, Norio

Hokeikyo Nyusu, (71), p.2 - 5, 2023/04

The TLD badge, a personal dosimeter using a thermoluminescence dosemeter, currently in operation at the Nuclear Fuel Cycle Engineering Laboratories of the Japan Atomic Energy Agency (JAEA-NCL), was developed in collaboration with Matsushita Industrial Co., Ltd. (now Panasonic System Solutions Japan Co., Ltd.), and was put into operation in 1982. Since then, the TLD badge has been used not only at NCL but also in Japan and overseas for a long time. However, the TLD badge system will no longer be accepted for new production by the manufacturer in 2019, and maintenance and repair services for the TLD readers will cease in 2027. In addition, a performance accreditation system for personal dosimetry will be introduced in Japan, and accredited personal dosemeters will be required under the revised enforcement regulations of the RI Law (from October 2023). Given these changes in the circumstance, NCL has decided to abandon the in-house measurement service and switch to commercially available accredited personal dosemeters in the future. In this paper, the development history and design concept of the TLD badge are outlined along with the historical development of the operational quantities, and the findings obtained from more than 40 years of operational experience with the TLD badge are presented.

Journal Articles

Lens dosimetry study in $$^{90}$$Sr+$$^{90}$$Y beta field; Full-face mask respirator shielding and dosemeter positioning

Tsujimura, Norio; Hoshi, Katsuya; Yamazaki, Takumi; Momose, Takumaro; Aoki, Katsunori; Yoshitomi, Hiroshi; Tanimura, Yoshihiko; Yokoyama, Sumi*

KEK Proceedings 2020-5, p.21 - 28, 2020/11

Journal Articles

Dataset of TLD badge response and hair activation for criticality accident neutron dosimetry

Tsujimura, Norio; Takahashi, Fumiaki; Takada, Chie

Progress in Nuclear Science and Technology (Internet), 6, p.148 - 151, 2019/01

JAEA Reports

Analytical evaluation of dose measurement of critical accident at SILENE (Contract research)

Nakamura, Takemi*; Tonoike, Kotaro; Miyoshi, Yoshinori

JAERI-Tech 2003-031, 38 Pages, 2003/03

JAERI-Tech-2003-031.pdf:3.97MB

Institute for Radioprotection and Nuclear Safety (IRSN) and the OECD Nuclear Energy Agency (NEA) jointly organized SILENE Accident Dosimetry Intercomparison Exercise to intercompare the dose measurement systems of participating countries. Each participating country carried out dose measurements in the same irradiation field, and the measurement results were mutually compared. The authors participated in the exercise to measure the doses of gamma rays and neutron from SILENE by using thermoluminescence dosimeters (TLD's) and an alanine dosimeter. In this examination, the authors derived evaluation formulae for obtaining a tissue-absorbed dose from measured value (ambient dose equivalent) of TLD for neutron. We reported the tissue-absorbed dose computed using this evaluation formula to OECD/NEA. TLD's for neutron were irradiated in the TRACY facility to verify the evaluation formulae. The results of TLD's were compared with the calculations of MCNP and measurements with alanine dose meter. We found that the ratio of the dose by the evaluation formula to the measured value by the alanine dosimeter was 0.94 and the formula agreed within 6%. From examination of this TRACY, we can conclude that the value reported to OECD/NEA has equivalent accuracy.

Journal Articles

Analyses of absorbed dose to tooth enamel against external photon exposure

Takahashi, Fumiaki; Yamaguchi, Yasuhiro; Iwasaki, Midori*; Miyazawa, Chuzo*; Hamada, Tatsuji*; Funabiki, Jun*; Saito, Kimiaki

Radiation Protection Dosimetry, 103(2), p.125 - 130, 2003/01

 Times Cited Count:4 Percentile:31.64(Environmental Sciences)

Absorbed dose to tooth enamels against external photon exposure was examined by the Electron Spin Resonance (ESR) dosimetry using tooth samples placed in a realistic physical phantom. Dose to teeth region was also measured with thermo-luminescence dosimeters (TLDs). A voxel-type phantom was constructed from CT images of the physical phantom. Monte Carlo calculations with this voxel-type phantom were performed to analyse the results of the experiments. The obtained data in this study were compared to the enamel doses, which were calculated with a modified MIRD-type and already given in a previous paper. The results suggested that the conversion factors from enamel dose to organ doses obtained by the modified MIRD-type phantom are to be applicable for retrospective individual dose assessments by the ESR dosimetry. The analysis, however, indicated that the size and figure of the head can affect the enamel dose for low photon energy region below 100keV.

Journal Articles

Conversion from tooth enamel dose to organ doses for ESR dosimetry

Takahashi, Fumiaki; Yamaguchi, Yasuhiro

Radiation Risk Assessment Workshop Proceedings, p.71 - 78, 2003/00

Conversion from tooth enamel dose to organ doses against external photon exposure were studied in order to develop a method that can retrospectively estimate organ doses by the Electron Spin Resonance (ESR) dosimetry using tooth samples. Monte Carlo calculations using EGS4 code were performed to obtain dose to tooth enamel and organ doses by using a modified MIRD-type phantom. The Electron Spin Resonance (ESR) dosimetry using tooth samples and dose measurements using thermo-luminescence dosimeters (TLDs) were also carried out to examine dose to teeth region with a realistic physical phantom. A Voxel-type phantom was constructed from CT images of the physical phantom. Monte Carlo calculations with the Voxel-type phantom were performed to verify the results of the experiments and enamel doses calculated by use of the modified MIRD-type phantom. The obtained data are to be useful for the retrospective assessment of individual dose in past exposure events by the ESR dosimetry with tooth enamel.

Journal Articles

Conversion from tooth enamel dose to organ doses for the electron spin resonance dosimetry

Takahashi, Fumiaki; Yamaguchi, Yasuhiro; Iwasaki, Midori*; Miyazawa, Chuzo*; Hamada, Tatsuji*; Saito, Kimiaki

Journal of Nuclear Science and Technology, 39(9), p.964 - 971, 2002/09

 Times Cited Count:6 Percentile:39.54(Nuclear Science & Technology)

Conversion from tooth enamel dose to organ doses was analyzed to establish a method of retrospective individual dose assessment against external photon exposure by the Electron Spin Resonance (ESR) dosimetry. Dose to tooth enamel was obtained by Monte Carlo calculations using a modified MIRD-type phantom. The calculated tooth enamel doses were verified by measurements with thermo-luminescence dosimeters inserted in a physical head phantom. Energy and angular dependences of tooth enamel dose were compared with those of other organ doses. Additional Monte Carlo calculations were performed to study the effects of human model on the tooth enamel dose with a voxel-type phantom, which was based on CT images of the physical phantom. The data derived with the modified MIRD-type phantom were applied to convert from tooth enamel dose to organ doses against external photon exposure in a hypothesized field, where scattered radiations were taken into account. The results indicated that energy distribution of photons incident to a human body should be required to evaluate precisely individual dose by the ESR dosimetry using teeth.

Journal Articles

Simple estimation method of $$gamma$$-ray dose using low neutron-sensitive TLD (UD-170LS) for Intra-Operative Boron Neutron Capture Therapy (IOBNCT)

Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya; Kishi, Toshiaki; Yamamoto, Tetsuya*; Matsumura, Akira*

Research and Development in Neutron Capture Therapy, p.499 - 503, 2002/09

In order to estimate the maximum gamma-ray dose in the brain in Intra-Operative Boron Neutron Capture Therapy (IOBNCT), this study was conducted for (1) the development of low neutron-sensitive TLD (UD-170LS-T2), (2) the correlation of capture gamma-ray dose profile in a phantom for various collimator sizes, and (3) the formula for simple estimation of maximum gamma-ray dose on IOBNCT. The sensitivity of TLD, as $$^{60}$$Co $$gamma$$-ray equivalent, for thermal neutron was 5.1$$pm$$0.8$$times$$10$$^{-14}$$($$^{60}$$Co-Gycm$$^{2}$$)The average relative deviations between predicted and measured $$gamma$$-ray dose for the mixed epithermal-thermal neutron beam in the phantom were $$pm$$8.5%. The accuracy of the $$gamma$$-ray dose determination in the clinical BNCT may be improved by this simple method.

Journal Articles

Analysis of dose in teeth for estimation of effective dose by the electron spin resonance (ESR) dosimetry using dental enamels

Takahashi, Fumiaki; Yamaguchi, Yasuhiro; Saito, Kimiaki; Iwasaki, Midori*; Miyazawa, Chuzo*; Hamada, Tatsuji*

KEK Proceedings 2000-20, p.48 - 55, 2000/12

no abstracts in English

JAEA Reports

None

Tsujimura, Norio; Shinohara, Kunihiko; Momose, Takumaro

PNC TN8410 98-083, 20 Pages, 1998/05

PNC-TN8410-98-083.pdf:0.62MB

None

Journal Articles

Nuclear heating measurements for SS-316, copper, graphite, tungsten, chromium, beryllium in a copper centered assembly bombarded with 14 MeV neutrons and analysis

Ikeda, Yujiro; Maekawa, Fujio; Kasugai, Yoshimi; Uno, Yoshitomo; A.Kumar*; M.Z.Youssef*; M.A.Abdou*; Konno, Chikara; Wada, Masayuki*

Fusion Engineering and Design, 42, p.289 - 297, 1998/00

 Times Cited Count:6 Percentile:49.22(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Report for marine environmental surveillance

; ; Isozaki, Tokuju; ; ; *

PNC TN8440 97-037, 501 Pages, 1997/10

PNC-TN8440-97-037.pdf:9.02MB

None

JAEA Reports

None

Tsujimura, Norio; Momose, Takumaro; Shinohara, Kunihiko

PNC TN8410 96-036, 20 Pages, 1996/02

PNC-TN8410-96-036.pdf:0.55MB

None

Journal Articles

Absorbed dose measurements and calculations in phantoms for 1.5 to 50keV photons

*; Tanaka, Shunichi; Nakane, Yoshihiro; Namito, Yoshihito*; Hirayama, Hideo*; Ban, Shuichi*;

Health Physics, 68(2), p.253 - 260, 1995/02

 Times Cited Count:9 Percentile:66.33(Environmental Sciences)

no abstracts in English

Journal Articles

Tritium production-rate measurement techniques developed at FNS/JAERI

Maekawa, Hiroshi; Maekawa, Fujio; Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; ; *

Fusion Technology, 26, p.1086 - 1091, 1994/11

no abstracts in English

Journal Articles

Results of the IAEA/RCA personal dosemeter intercomparison in the Asian and Pacific region

Murakami, Hiroyuki; Minami, Kentaro; R.V.Griffith*

Radiation Protection Dosimetry, 54(1), p.19 - 23, 1994/00

 Times Cited Count:4 Percentile:42.35(Environmental Sciences)

no abstracts in English

JAEA Reports

None

; ; Komatsuzaki, Kenji;

PNC TN8520 93-002, 191 Pages, 1993/03

PNC-TN8520-93-002.pdf:4.47MB

None

JAEA Reports

None

PNC TJ1500 93-001, 96 Pages, 1993/03

PNC-TJ1500-93-001.pdf:3.92MB

None

JAEA Reports

None

Kurosawa, Ryuhei*

PNC TJ1615 92-002, 23 Pages, 1992/03

PNC-TJ1615-92-002.pdf:1.54MB

None

JAEA Reports

Development of a glow curve measuring system of TLDs and its applications

*; Tanaka, Shunichi; Yoshizawa, Michio; Hirayama, Hideo*; Ban, Shuichi*; ; *; Nakane, Yoshihiro

JAERI-M 92-023, 37 Pages, 1992/03

JAERI-M-92-023.pdf:0.78MB

no abstracts in English

41 (Records 1-20 displayed on this page)