Fluorescence X-ray field for radiation dosemeters calibration

Tsuji, Tomoya; Yoshitomi, Hiroshi; Sato, Fuminobu*; Tanimura, Yoshihiko

Radiation Protection Dosimetry, p.ncaf060_1 - ncaf060_15, 2025/00

https://doi.org/10.1093/rpd/ncaf060

Improved multicomponent analysis method for electron spin resonance spectra of gamma-irradiated tooth enamel

Yamashita, Takuma*; Iwami, Satone*; Mitsuyasu, Yusuke*; Ono, Kenta*; Oka, Toshitaka; Takahashi, Atsushi*; Kino, Yasushi*; Sekine, Tsutomu*; Shimizu, Yoshinaka*; Chiba, Mirei*; et al.

KEK Proceedings 2024-6, p.85 - 90, 2024/12

To clarify the radiation effects of the accident at the TEPCO's Fukushima Daiichi NPP on living organisms, it is important to accurately estimate the dose to each individual. We have developed a multi-component analysis program using random number optimization to extract only the components derived from carbonate radicals from the ESR spectra.

Cavity ionization chamber responses in the JAEA and the NMIJ high-energy photon reference fields for radiation protection

Ishii, Junya*; Shimizu, Morihito*; Kato, Masahiro*; Kurosawa, Tadahiro*; Tsuji, Tomoya; Yoshitomi, Hiroshi; Tanimura, Yoshihiko; Watabe, Hiroshi*

Journal of Radiological Protection, 44(3), p.031516_1 - 031516_8, 2024/09

https://doi.org/10.1088/1361-6498/ad7a07

Present and new operational quantities evaluated from photon spectrum measurements at workplaces in the research reactor and accelerator facility at the JAEA

Tanimura, Yoshihiko; Yoshitomi, Hiroshi; Nishino, Sho; Tsuji, Tomoya; Fukami, Tomoyo; Shinozuka, Tomoki; Oishi, Kohei; Ishii, Masato; Takamiya, Kei; Onuki, Takaya; et al.

Radiation Measurements, 176, p.107196_1 - 107196_6, 2024/08

https://doi.org/10.1016/j.radmeas.2024.107196

The ICRU has proposed to change the definitions of the operational quantities used for the area and individual monitoring for external exposure in the ICRU Report 95. As introducing the new operational quantities into the radiation monitoring may affect the dose assessment results using the present personal dosimeters, it is necessary to characterize the energy spectrum in the workplace and the energy dependency of the dosimeters to be used. In this work the photon spectra were measured using a NaI(Tl) scintillation detector or a LaBr(Ce) scintillation detector at the workplaces in the Japanese Research Reactor No.3 (JRR-3) and the Japan Proton Accelerator Research Complex (J-PARC) at Japan Atomic Energy Agency (JAEA). Then the present and new operational quantities were evaluated using the above mention spectra at the workplaces and compared each other.

Annual report of Nuclear Science Research Institute, JFY2021

Nuclear Science Research Institute, Sector of Nuclear Science Research

JAEA-Review 2023-050, 178 Pages, 2024/03

JAEA-Review-2023-050.pdf:7.06MB

Nuclear Science Research Institute (NSRI) is composed of Planning and Management Department and six departments, namely Department of Operational Safety Administration, Department of Radiation Protection, Engineering Services Department, Department of Research Reactor and Tandem Accelerator, Department of Criticality and Hot Examination Technology and Department of Decommissioning and Waste Management, and each department manages facilities and develops related technologies to achieve the "Medium- to Long- term Plan" successfully and effectively. And, four research centers which are Advanced Science Research Center, Nuclear Science and Engineering Center, Nuclear Engineering Research Collaboration Center and Materials Sciences Research Center, belong to NSRI. In order to contribute the future research and development and to promote management business, this annual report summarizes information on the activities of NSRI of JFY 2021 as well as the activity on research and development carried out by Collaborative Laboratories for Advanced Decommissioning Science, Nuclear Safety Research Center and activities of Nuclear Human Resource Development Center, using facilities of NSRI.

Characterization of small radiophotoluminescence dosemeter in terms of (0.07) for extremity dose monitoring of medical personnel

Kowatari, Munehiko*; Yoshitomi, Hiroshi; Nagamoto, Keisuke*; Nakagami, Koichi*; Moritake, Takashi*; Kunugita, Naoki*

Radiation Protection Dosimetry, 199(15-16), p.1807 - 1812, 2023/10

https://doi.org/10.1093/rpd/ncac259

Establishment of JIS testing laboratory for radiation monitoring instruments

Yoshitomi, Hiroshi

Isotope News, (786), p.26 - 29, 2023/04

no abstracts in English

Development of portable thyroid monitoring system with detector shields

Tanimura, Yoshihiko

FBNews, (548), p.1 - 5, 2022/08

In the situation of a severe nuclear accident, radioiodine monitoring in thyroid should be performed for a large number of people immediately after accident. The portable thyroid dose monitoring system with the radiation shield which can be used in a high dose rate condition has been developed. In this paper, the outline of the monitoring system and the performance test results using the system will be described.

Evaluation of a one-dimensional position-sensitive quartz optical fiber sensor based on the time-of-flight method for high radiation dose rate applications

Terasaka, Yuta; Watanabe, Kenichi*; Uritani, Akira*

Nuclear Instruments and Methods in Physics Research A, 996, p.165151_1 - 165151_8, 2021/04

https://doi.org/10.1016/j.nima.2021.165151

For the measurement of radiation distribution inside the Fukushima Daiichi Nuclear Power Station (FDNPS) buildings, the evaluation of a small-diameter quartz optical fiber as a one-dimensional position-sensitive sensor was conducted. The sensor determines the incident position of radiation into the fiber using the time-of-flight information of emitted Cerenkov photons in the optical fiber. Compared with the conventional sensor using the plastic scintillating fiber, the quartz optical fiber has much higher position resolution, which may be the result of the improvement of timing characteristics caused by the prompt emission mechanism of the Cerenkov radiation. Additionally, the response of position-sensitive quartz optical fiber sensor under high radiation field was evaluated, and good count rate linearity was confirmed using the 10 m long quartz optical fiber with a diameter of 0.4 mm up to the dose rate at least 20 mSv/h, and the radiation tolerance property up to the accumulated dose of 1 kGy was evaluated.

Attempt to estimate the background pulse height spectrum of the CeBr scintillation spectrometer due to terrestrial gamma ray components; Application in environmental radiation monitoring

Kowatari, Munehiko; Tanimura, Yoshihiko; Kessler, P.*; Rttger, A.*

Radiation Measurements, 138, p.106431_1 - 106431_6, 2020/11

https://doi.org/10.1016/j.radmeas.2020.106431