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

古渡 意彦; 谷村 嘉彦; Kessler, P.*; Rttger, A.*

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

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

In radiological emergency, timely and reliable radiological information such as dose rate or radioactive concentrations due to artificial radionuclides is indispensable to protect general public and the first responder of the situation. The authors have investigated the method for effectively identifying and determining the radioactivity concentration using a scintillation spectrometer. In this study, the authors demonstrate how influence of terrestrial background (BG) component on measured pulse height spectrum can be minimized to obtain the peaks from gamma rays emitted by artificial radioactivity. In some cases of radiological emergency monitoring, subtraction of BG components was probe to be difficult, because the prior measurement of BG component at the place to be monitored is compulsory. By removing the BG component appropriately from measured pulse height spectrum without any prior BG measurement, the effective minimum detection limit of the spectrometer would be declined.

A Cubic CeBr gamma-ray spectrometer suitable for the decommissioning of the Fukushima Daiichi Nuclear Power Station

冠城 雅晃; 島添 健次*; 大鷹 豊*; 上ノ町 水紀*; 鎌田 圭*; Kim, K. J.*; 吉野 将生*; 庄子 育宏*; 吉川 彰*; 高橋 浩之*; et al.

Nuclear Instruments and Methods in Physics Research A, 971, p.164118_1 - 164118_8, 2020/08

https://doi.org/10.1016/j.nima.2020.164118

Our work focused on the passive gamma-ray analysis (PGA) of the nuclear fuel debris based on measuring gamma rays with an energy greater than 1 MeV for the decommissioning of the Fukushima Daiichi Nuclear Power Station (FDNPS). The PGA requires gamma-ray spectrometers to be used under the high dose rates in the FDNPS, then we fabricated a small cubic CeBr spectrometer with dimensions of 5 mm 5 mm 5 mm, coupled to a Hamamatsu R7600U-200 photomultiplier tube (PMT). The performance at dose rates of 4.4 to 750 mSv/h in a Co field was investigated. The energy resolution (FWHM) at 1333 keV ranged from 3.79% to 4.01%, with a standard deviation of 6.9%, which met the narrow gamma decay spectral lines between Eu (1274 keV) and Co (1333 keV). However, the spectra shifted to a higher energy level as the dose rate increase, there was a 51% increase at the dose rates of 4.4 to 750 mSv/h, which was caused by the PMT gain increase.

Prototype test of a portable thyroid dose monitoring system using gamma-ray spectrometers

西野 翔; 谷村 嘉彦; 吉富 寛; 高橋 聖

Radiation Measurements, 134, p.106292_1 - 106292_5, 2020/06

https://doi.org/10.1016/j.radmeas.2020.106292

原子力災害発生時においては、多数の住民・作業者を対象とした甲状腺ヨウ素モニタリングを、事故後速やかに実施する必要がある。日本原子力研究開発機構では、災害時の高バックグラウンド線量率下でも使用可能な可搬型甲状腺モニタの開発を行っている。本発表では、製作した甲状腺モニタ試作機の性能試験で得られた結果を報告する。

Conversion factor from dosemeter reading to air kerma for nuclear worker using anthropomorphic phantom for further conversion from air kerma to organ-absorbed dose

古田 裕繁*; 辻村 憲雄; 西出 朱美*; 工藤 伸一*; 三枝 新*

Radiation Protection Dosimetry, 189(3), p.371 - 383, 2020/05

https://doi.org/10.1093/rpd/ncaa051

Estimation of cancer risk based on the organ-absorbed dose is underway for the Japanese Epidemiological Study on Low-Dose Radiation Effects (J-EPISODE). The reconstruction method for the organ-absorbed dose follows the approach adopted in the IARC 15-Country Collaborative Study, which examined the dosemeter response to photon exposure for the old film badge (FB) type, a multi-element FB and a thermoluminescence dosemeter. Until 2000, the dosemeters used in Japan were almost the same in the IARC study, so IARC study data could be used as they were. However, since 2000, the type of dosemeter has been replaced with active personal dosemeters (hereafter called electronic personal dosemeters), radio-photoluminescent glass dosemeters (Glass badge) and optically stimulated luminescence dosemeters (Luminess badge). Hence, it was necessary to collect these data again. A dosemeter response experiment was conducted using a device that irradiated an anthropomorphic phantom in the Japan Atomic Energy Agency calibration laboratories. The aim of the paper is to provide a conversion factor from reading in terms of (10) to air kerma for realistic conditions for further conversion from air kerma to organ-absorbed dose. The obtained dosemeter responses for the dosemeter types currently used in Japan were consistent with those in the IARC study. These data will be utilized for J-EPISODE in reconstructing the organ-absorbed dose.

A Study of a calibration technique for a newly developed thyroid monitor and its uncertainties due to body size for radioiodine measurements

吉富 寛; 西野 翔; 谷村 嘉彦; 高橋 聖

Radiation Measurements, 133, p.106279_1 - 106279_6, 2020/04

https://doi.org/10.1016/j.radmeas.2020.106279

緊急時の高線量率下で、公衆及び作業者の甲状腺に蓄積した放射性ヨウ素を簡便かつ精度よく定量するための可搬型甲状腺モニタを開発している。本甲状腺モニタは2個のLaBr(Ce)検出器(公衆用)もしくは、2個のCZT検出器(作業者用)を遮蔽体内に内包し、被検者の甲状腺内の放射性ヨウ素を定量するものである。これまでに、数値計算と簡易物理ファントムを組み合わせ、甲状腺及び周囲組織の詳細な解剖学的形状を反映した標準ボクセルファントムをベースとした校正方法を開発してきた。しかしながら、校正に用いた標準ボクセルファントムと被検者の体格の個人差によって、計数効率が変化し、放射性ヨウ素の定量の精度に影響を及ぼすことが懸念されてきた。そこで、8種類の甲状腺形状等が異なるボクセルファントムと、甲状腺体積及び甲状腺前組織厚を変化させたボクセルファントムに対して本甲状腺モニタの計数効率を計算評価した。その結果、甲状腺前組織厚の変化は計数効率に与える影響が大きいが、その程度は高々25 %であることが明らかになった。

Establishment of a low dose rate gamma ray calibration field for environmental radiation monitoring devices

古渡 意彦; 吉富 寛; 西野 翔; 谷村 嘉彦; 大石 哲也; Kessler, P.*; Neumaier, S.*; Rttger, A.*

Radiation Protection Dosimetry, 187(1), p.61 - 68, 2019/12

https://doi.org/10.1093/rpd/ncz138

A low dose rate Cs gamma ray calibration field that fully satisfies the requirement of the ISO 4037 series was established in the Facility of Radiation Standards in Japan Atomic Energy Agency. Two different methods were employed to determine the reference air kerma rate, namely a conventional ionization chamber and a G(E) function method used a newly developed scintillation spectrometer. To fulfill the requirement of the ISO 4037 and suppress scattering of Cs gamma ray within the room as far as possible, a suitable lead collimator was introduced to limit the irradiation area at test points and placed at the middle height in an irradiation room with a grating floor. From measured results evaluated reference air kerma rates between 1.0 m and 3.0 m from the center of the source, gamma ray scattering from the room structures was found to be negligible. The resulting Cs gamma ray calibration field could provide ambient dose equivalent rates of 0.7-7.2 Sv h for use with environmental radiation monitoring devices.

Assessment of inhomogeneity of exposure to radiation workers in homogeneous exposure situations in Nuclear Industry and Accelerator Facility by using Monte Carlo calculations coupled with a mathematical phantom; Exposure to the lens of the eye in homogeneous exposure situation due to gamma and beta rays

古渡 意彦; 吉富 寛

Radioisotopes, 68(9), p.595 - 603, 2019/09

https://doi.org/10.3769/radioisotopes.68.595

The recommended annual limit of equivalent dose to the lens of the eye has decreased to 20 mSv y from the current limit of 150 mSv y. In terms of occupational exposure to radiation workers, exposure inhomogeneity plays an important role when estimating the eye lens dose from readings of dosimeters worn by workers on their trunk. The authors focused on homogeneous exposure situations that radiation workers may encounter in nuclear and accelerator facilities. Moreover, the authors investigated how radiation workers are exposed non-homogeneously in homogeneous exposure scenarios, where radiation workers may usually be encountered, regardless of their radiation works. In our previous study, we proposed a methodology to quantitatively evaluate the inhomogeneity of exposure. The homogeneity of exposure was evaluated by performing Monte Carlo calculations with a mathematical phantom under the isotropic and rotational irradiation geometries due to gamma and beta rays. (3)/(10) exceeded 1.0 even in the case of homogeneous exposure to gamma rays. Even in the homogeneous exposure scenarios, the (3) might exceed the revised annual dose limit for radiation workers who are exposed close to annual dose limit.

Characteristics of commercially available CdZnTe detector as gamma-ray spectrometer under severe nuclear accident

谷村 嘉彦; 西野 翔; 吉富 寛; 古渡 意彦; 大石 哲也

Progress in Nuclear Science and Technology (Internet), 6, p.134 - 138, 2019/01

https://doi.org/10.15669/pnst.6.134

福島第一原子力発電所事故のような原子力災害時においては、様々な放射性物質が環境中に放出され、線量を増加させることが考えられる。線スペクトルを測定し、核種を同定することは外部被ばくと内部被ばくの両方に対する放射線防護上重要である。そこで、市販のCdZnTeスペクトロメータを選び、線入射角度依存性と使用可能な線量率範囲をFRSの校正場で試験した。その結果、全体の85%をカバーできる135において感度低下は15%以下であり、200Gy/h以下の空気カーマ率の場においてスペクトルが測定できることがわかった。

Development of a high-efficiency proton recoil telescope for D-T neutron fluence measurement

谷村 嘉彦; 吉澤 道夫

Radiation Protection Dosimetry, 180(1-4), p.417 - 421, 2018/08

BB2016-1356.pdf:0.59MB

https://doi.org/10.1093/rpd/ncx278

放射線標準施設(FRS)に整備された14.8MeV単色中性子校正場の中性子フルエンスを測定するために、一組のラジエータ、E検出器及びE検出器からなる高効率反跳陽子テレスコープ(PRT)を開発した。ラジエータには、2mmの厚いプラスチックシンチレーション検出器を採用することにより、検出効率を向上させるとともに、ラジエータ内での反跳陽子のエネルギー損失を補償可能とした。E及びE検出器には、それぞれ150m及び3mmの有感層を持つシリコン半導体検出器を採用した。ラジエータ-E検出器間の距離を、50mm, 100mm及び150mmに変化させたときの検出効率を14,8MeV校正場での試験結果を基に評価した。検出効率は、距離の減少とともに、最大3.710まで増加した。これは、通常のPRTよりも数桁高く、FRSの14.8MeV校正場での中性子フルエンス測定が数時間で可能な検出効率である。

Comprehensive study on the response of neutron dosimeters in various simulated workplace neutron calibration fields

西野 翔; 星 勝也; 辻村 憲雄; 古渡 意彦; 吉田 忠義

Proceedings of 14th International Congress of the International Radiation Protection Association (IRPA-14), Vol.3 (Internet), p.1258 - 1263, 2017/11

http://www.irpa.net/docs/IRPA14%20Proceedings%20Volume%203.pdf

連続中性子場における線量計の応答特性を理解するために、日本原子力研究開発機構の放射線標準施設棟(FRS)及び計測機器校正施設(ICF)に整備された種々の作業環境模擬中性子校正場において、形状・検出方式の異なる4種類の中性子サーベイメータの特性試験を実施した。その結果、1MeV以下のエネルギー領域にのみ中性子フルエンス分布をもつ校正場においては、いずれのサーベイメータも、中性子線量を大きく過大または過小評価することが分かった。本発表では、場の中性子スペクトルと線量計応答の関係を示し、中性子線量計の校正のあり方について議論を行う。