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

辻村 憲雄; 星 勝也; 山崎 巧; 百瀬 琢麿; 青木 克憲; 吉富 寛; 谷村 嘉彦; 横山 須美*

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

To investigate the shielding effects of full-face respirator masks and the suitable positioning of lens dosemeters, irradiation experiments of $$^{90}$$Sr+$$^{90}$$Y beta particles were performed using an anthropomorphic head phantom into the eyes of which small thermoluminescence dosemeters (TLDs) were loaded, and the lens doses measured by these TLDs were compared with the doses measured by commercially available personal dosemeters attached around the eyes of the phantom. The three tested masks reduced the beta lens dose to 9-14% as compared to the lens doses in the absence of a mask. As for the suitable positioning of lens dosemeters, the $$H_{rm p}$$(0.07) evaluated by the $$H_{rm p}$$(0.07) dosemeter attached at the center of the forehead gave an over-response to the lens dose by a factor of 2.5-8.4 regardless of the presence of masks. The $$H_{rm p}$$(3) evaluated by the $$H_{rm p}$$(3) dosemeters, even though placed at extreme positions near the outside corners of the eyes, provided better lens dose estimates with a response of 0.38-1.7.


Measurements of the doses of eye lens for the workers of Fukushima Daiichi Nuclear Power Plant

横山 須美*; 江崎 巌*; 立崎 英夫*; 立木 秀一*; 平尾 一茂*; 青木 克憲; 谷村 嘉彦; 星 勝也; 吉富 寛; 辻村 憲雄

Radiation Measurements, 138, p.106399_1 - 106399_5, 2020/11


In Japan, the possibility to change the current dose limit of the lens of the eye for the radiation workers working in the planned exposure situation (normal controlled situations) to a new ICRP dose limit was discussed. It was further discussed how to appropriately monitor and manage the equivalent dose of the eye lenses for these workers exposed to radiation at their workplaces, such as nuclear and medical facilities. Among the workers exposed to a high-dose radiation at the water storage flange tank deconstructed $$^{90}$$Sr/$$^{90}$$Y dominant areas and the nuclear reactor buildings (high dose gamma-ray) of the Fukushima Daiichi Nuclear Power Plant (1F-NPP), H$$_{p}$$(10), H$$_{p}$$(3), and H$$_{p}$$(0.07) at the head and the chest (or the upper arm) were estimated by passive personal dosimeters using thermoluminescence dosimeters (TLDs) and radio photoluminescence glass dosimeters (RPLGDs). The relationship between H$$_{p}$$(10), H$$_{p}$$(3), and H$$_{p}$$(0.07) along with the effects of the sites of wearing dosimeters on the head inside a full-face mask and the chest (or upper arm) were discussed.


Attempt to estimate the background pulse height spectrum of the CeBr$$_{3}$$ scintillation spectrometer due to terrestrial gamma ray components; Application in environmental radiation monitoring

古渡 意彦; 谷村 嘉彦; Kessler, P.*; R$"o$ttger, A.*

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


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.


Background correction method for portable thyroid dose monitor using gamma-ray spectrometer developed at JAEA in high dose rate environment

谷村 嘉彦; 吉富 寛; 西野 翔; 高橋 聖

Radiation Measurements, 137, p.106389_1 - 106389_5, 2020/09

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Eye lens dosimetry for workers at Fukushima Daiichi Nuclear Power Plant, 2; Field study using humanoid phantoms

辻村 憲雄; 星 勝也; 青木 克憲; 吉富 寛; 谷村 嘉彦; 横山 須美*

Radiation Measurements, 134, p.106305_1 - 106305_5, 2020/06

 被引用回数:1 パーセンタイル:100(Nuclear Science & Technology)

We performed a field study of eye lens dosimetry for workers involved in the decommissioning operation at the Fukushima Daiichi Nuclear Power Plant. In this study, humanoid phantoms equipped with different personal dosemeters were placed at selected locations in the workplace. The experiment showed that $$H_{rm p}$$(3) at the head is about 20% higher than $$H_{rm p}$$(10) (or $$H_{rm p}$$(3)) at the trunk. This level of dose gradient is generally interpreted as being "almost uniform" in radiological control; therefore, tasks conducted in open areas with such relatively small dose gradients ($$sim$$1.2) will not require specific monitoring with eye lens dosemeters, except when the eye lens dose approaches the dose limit.


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

 被引用回数:2 パーセンタイル:8.37(Nuclear Science & Technology)



Eye lens dosimetry for workers at Fukushima Daiichi Nuclear Power Plant, 1; Laboratory study on the dosemeter position and the shielding effect of full face mask respirators

星 勝也; 吉富 寛; 青木 克憲; 谷村 嘉彦; 辻村 憲雄; 横山 須美*

Radiation Measurements, 134, p.106304_1 - 106304_5, 2020/06

 被引用回数:1 パーセンタイル:100(Nuclear Science & Technology)



Experimental determination of anisotropic emission of neutrons from $$^{252}$$Cf neutron source with the spherical protection case

古渡 意彦; 西野 翔; Romallosa, K. M. D.*; 吉富 寛; 谷村 嘉彦; 大石 哲也

Radiation Protection Dosimetry, 189(4), p.436 - 443, 2020/05




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

 被引用回数:2 パーセンタイル:8.37(Nuclear Science & Technology)

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$$_{3}$$(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.*; R$"o$ttger, A.*

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

 被引用回数:1 パーセンタイル:58.8(Environmental Sciences)

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 $$mu$$Sv h$$^{-1}$$ for use with environmental radiation monitoring devices.


Corrigendum; 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.*; R$"o$ttger, A.*

Radiation Protection Dosimetry, 186(4), P. 538, 2019/12

 被引用回数:0 パーセンタイル:100(Environmental Sciences)

原著論文の表5(B)中の単位について、nSv h$$^{-1}$$とすべきところ$$mu$$Sv h$$^{-1}$$と記載するミスがあったため、訂正する。


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



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

 被引用回数:0 パーセンタイル:100(Environmental Sciences)

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、$$Delta$$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。$$Delta$$E及びE検出器には、それぞれ150$$mu$$m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3.7$$times$$10$$^{-3}$$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。


Investigation of main radiation source above shield plug of Unit 3 at Fukushima Daiichi Nuclear Power Station

平山 英夫*; 近藤 健次郎*; 鈴木 征四郎*; 谷村 嘉彦; 岩永 宏平*; 永田 寛*

EPJ Web of Conferences, 153, p.08010_1 - 08010_3, 2017/09

 被引用回数:0 パーセンタイル:100

福島第一原子力発電所3号機のシールドプラグ上は高線量率となっており、この主要な線源を調査するために鉛製コリメータ付CdZnTe検出器を用いて光子線の波高分布を測定した。その結果、低エネルギー光子線の寄与が大きいことがわかった。0.662MeV光子のピーク計数率から、60cm厚コンクリート製のシールドプラグ1層目下部のCs-137放射能密度は、8.1$$times$$10$$^9$$ $$sim$$ 5.7$$times$$10$$^{10}$$Bq/cm$$^2$$であると評価された。Cs-137が、半径6mのシールドプラグの下部隙間に、シールドプラグ上5箇所で評価した放射能密度の平均値2.6$$times$$10$$^{10}$$Bq/cm$$^2$$で均一に付着しているとすると、Cs-137の合計放射能は30PBqと見積もられる。



谷村 嘉彦; 富田 純平; 吉富 寛; 吉澤 道夫; 箱崎 亮三*; 高橋 荘平*

保健物理, 51(3), p.141 - 146, 2016/09



Development of the graphite-moderated neutron calibration fields using $$^{241}$$Am-Be sources in JAEA-FRS

西野 翔; 谷村 嘉彦; 江幡 芳昭*; 吉澤 道夫

Journal of Radiation Protection and Research, 41(3), p.211 - 215, 2016/09



Determination of low-level radiostrontium, with emphasis on ${it in situ}$ pre-concentration of Sr from large volume of freshwater sample using Powdex resin

富田 純平; 山本 政儀*; 野崎 天生; 谷村 嘉彦*; 大石 哲也

Journal of Environmental Radioactivity, 146, p.88 - 93, 2015/08

 被引用回数:7 パーセンタイル:66(Environmental Sciences)

An improved analytical method was developed for determining of low levels of radiostrontium in environmental freshwater samples. Emphasis was placed to the in situ pre-concentration of radiostrontium with Powdex resin in large volumes (100-300 L) of freshwater samples from many locations without using of deleterious substances such as NaOH and mineral acids. Measuring electric conductivity (EC) of water samples enabled the estimation of the amount of Powdex resin required for quantitative recovery of Sr from the large water samples in the field. The Powdex resin that adsorbed Sr was brought back to the laboratory, and Sr adsorbed in the resin was eluted by 8 M HNO$$_{3}$$ together with Sr carrier added. Strontium was radiochemically separated by the cation exchange method for $$beta$$ counting after removal of most of the Ca using Ca(OH)$$_{2}$$ precipitation. Through the procedure the Sr chemical yield was 88% on average. This analytical method was verified by analyzing 170 L of water samples with different salinity values, to which a known amount of $$^{90}$$Sr was added. The detection limits of $$^{90}$$Sr activities obtained using the 170 L water samples was estimated to be approximately 0.1 mBq L$$^{-1}$$ for a counting time of 100 min. The method was also applied to environmental samples collected from Ibaraki and Fukushima prefectures; their $$^{90}$$Sr activities ranged from 0.16 to 0.93 mBq L$$^{-1}$$.


Series studies on inter-comparison of radiation calibration fields and calibration techniques between KAERI and JAEA

吉富 寛; 谷村 嘉彦*; 立部 洋介; 堤 正博; 川崎 克也; 古渡 意彦; 吉澤 道夫; 清水 滋*; Kim, J.-S.*; Lee, J.-G.*; et al.

Proceedings of 4th Asian and Oceanic Congress on Radiation Protection (AOCRP-4) (CD-ROM), 4 Pages, 2015/07

A series inter-comparison regarding basic quantities of radiation calibration fields and calibration techniques has been made between KAERI and JAEA since 2006. Air kerma rates of the ISO narrow series X-ray calibration fields and neutron spectra at a point of test in each institute and results revealed that KAERI and FRS-JAEA maintained well-defined calibration fields for X-ray and D$$_{2}$$O-Cf neutron calibration fields. Intensive calibrations of personal dosimeters in RI neutron calibration fields and beta-ray calibration fields were performed in both institutes. Results of calibration factors indicate that almost identical calibration factors could be obtained.


Measurement of air kerma rates for 6- to 7-MeV high-energy $$gamma$$-ray field by ionisation chamber and build-up plate

古渡 意彦; 谷村 嘉彦; 堤 正博

Radiation Protection Dosimetry, 162(4), p.446 - 458, 2014/12

 被引用回数:3 パーセンタイル:68.51(Environmental Sciences)



Photon dose mixed in monoenergetic neutron calibration fields using $$^7$$Li(p,n)$$^7$$Be reaction

谷村 嘉彦; 堤 正博; 吉澤 道夫

Radiation Protection Dosimetry, 161(1-4), p.149 - 152, 2014/10

 被引用回数:0 パーセンタイル:100(Environmental Sciences)

放射線標準施設では、静電加速器を利用した単色中性子校正場を、8keVから19MeVのエネルギー範囲で開発している。このうち、144, 250, 565keV校正場では、LiFターゲットに陽子を入射して引き起こされる$$^7$$Li(p,n)$$^7$$Be反応を利用して単色中性子を発生させている。ところが、これ以外の反応で発生した光子が、校正に影響を与える可能性があるため、この線量を評価する必要がある。そこで、中性子とターゲット・室内構造物との核反応で発生する光子をMCNP-ANTコードで計算した。そして、単色中性子に対する周辺線量当量H*(10)の比を評価した。

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