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Kinetic inductance neutron detector operated at near critical temperature

Vu, TheDang; 西村 和真*; 宍戸 寛明*; 原田 正英; 及川 健一; 宮嶋 茂之*; 日高 睦夫*; 奥 隆之; 曽山 和彦; 相澤 一也; et al.

Journal of Physics; Conference Series, 1590, p.012036_1 - 012036_9, 2020/07

Our CB-KID neutron imager detects high spatial resolution neutrons transmission images by using a delay-line technique. We found that the number of events was remarkably increased with increasing the detector temperature until close to the critical temperature Tc. We investigated the properties of CB-KID at near Tc. We observed systematic changes of neutron signals as a function of the detector temperature from 4 K to Tc. The simulations modeled the sequential physical processes for $$^{10}$$B(n,$$alpha$$)$$^{7}$$Li reactions and energy deposition by particles within CB-KID, including neutrons, $$^{4}$$He particles, $$^{7}$$Li particles, photon and electron transport.


Remote detection of radioactive hotspot using a Compton camera mounted on a moving multi-copter drone above a contaminated area in Fukushima

佐藤 優樹; 小澤 慎吾*; 寺阪 祐太; 峯本 浩二郎*; 田村 智志*; 新宮 一駿*; 根本 誠*; 鳥居 建男

Journal of Nuclear Science and Technology, 57(6), p.734 - 744, 2020/06

 被引用回数:1 パーセンタイル:19.53(Nuclear Science & Technology)

The Fukushima Daiichi Nuclear Power Station, operated by Tokyo Electric Power Company Holdings, Inc., suffered a meltdown as a result of a large tsunami triggered by the Great East Japan Earthquake on March 11, 2011. To proceed with the environmental recovery by decontamination, drawing a radiation distribution map that can indicate the distribution of radioactive substances is extremely important to establish detailed decontamination plans. We developed a remote radiation imaging system consisting of a lightweight Compton camera and a multi-copter drone to remotely measure the distribution of the radioactive substances. This system can perform radiation imaging using a Compton camera while flying and moving. In addition, it is also possible to draw the distribution of radioactive substances three-dimensionally by projecting the radiation image measured with the Compton camera on a three-dimensional topography model separately acquired by a 3D-LiDAR. We conducted a survey of radioactive hotspots in difficult-to-return zone in the coastal area of Fukushima, Japan. The drone system succeeded in three-dimensional visualization of several hotspots deposited on the ground. Such remote technology would be useful not only for monitoring the difficult-to-return zone, but also for monitoring distribution of radioactive substances inside the site of the FDNPS where decommissioning work is ongoing.


Gamma detector response simulation inside the pedestal of Fukushima Daiichi Nuclear Power Station

Riyana, E. S.; 奥村 啓介; 寺島 顕一; 松村 太伊知; 坂本 雅洋

Mechanical Engineering Journal (Internet), 7(3), p.19-00543_1 - 19-00543_8, 2020/06

Prediction of the fuel debris location and distribution inside the primary containment vessel (PCV) of the Fukushima Daiichi Nuclear Power Plant is important to decide further decommissioning step and strategy. The radiation measurements in the past internal investigations have not yet provided enough information to predict fuel debris location and its distribution inside PCV. To support further measurement efforts, we simulate the detector response inside the PCV. The calculation result could provide a base on deciding suitable detector systems to assist the efforts on searching, localizing and defining distributions of the fuel debris.


A Study of directional gamma-ray detector without shield by Monte Carlo simulation

北山 佳治; 寺阪 祐太; 佐藤 優樹; 鳥居 建男

Proceedings of International Youth Nuclear Congress 2020 (IYNC 2020) (Internet), 4 Pages, 2020/05

At the Fukushima Daiichi Nuclear Power Station (FDNPS), various works are under-way for decommissioning. Depending on work places, there are radioactive hotspot. Therefore measuring the position of the hotspot in advance is important for safety of the worker. The system that can easily measure the dose rate distribution in work place has been demanded. There are two methods for imaging a dose rate distribution: a pinhole camera and a Compton camera. A pinhole camera can determine direction of radiation source in one event, but the weight becomes heavy because a shield is required. On the other hand, since the Compton camera does not require a shield, it can be reduced in the size and weight. However, Compton imaging method generate many ghosts of cone traces, which reduce the signal-to-noise ratio. We propose a new gamma-ray imager that works like a pinhole camera without a shield. This is achieved by arranging directional gamma ray detectors that does not require a shield. In this work, we have performed principle verification of a directional gamma-ray detector that is a basic component of the new gamma-ray imager by using Geant4 Monte Carlo simulation.


放射線耐性の高い薄型SiC中性子検出器の開発(委託研究); 平成30年度英知を結集した原子力科学技術・人材育成推進事業

廃炉国際共同研究センター; 京都大学*

JAEA-Review 2019-042, 43 Pages, 2020/03




先端計測技術の融合で実現する高耐放射線燃料デブリセンサーの研究開発(委託研究); 平成30年度英知を結集した原子力科学技術・人材育成推進事業

廃炉国際共同研究センター; 高エネルギー加速器研究機構*

JAEA-Review 2019-040, 77 Pages, 2020/03




レーザー加工により発生する微粒子の解析と核種同定手法の開発(委託研究); 平成30年度英知を結集した原子力科学技術・人材育成推進事業

廃炉国際共同研究センター; 東京大学*

JAEA-Review 2019-034, 59 Pages, 2020/03




Monte Carlo radiation transport modelling of the current-biased kinetic inductance detector

Malins, A.; 町田 昌彦; Vu, TheDang; 相澤 一也; 石田 武和*

Nuclear Instruments and Methods in Physics Research A, 953, p.163130_1 - 163130_7, 2020/02

 被引用回数:2 パーセンタイル:6.04(Instruments & Instrumentation)

Radiation transport simulations were used to analyse neutron imaging with the current-biased kinetic inductance detector (CB-KID). The PHITS Monte Carlo code was applied for simulating neutron, $$^{4}$$He, $$^{7}$$Li, photon and electron transport, $$^{10}$$B(n,$$alpha$$)$$^{7}$$Li reactions, and energy deposition by particles within CB-KID. Slight blurring in simulated CB-KID images originated $$^{4}$$He and $$^{7}$$Li ions spreading out in random directions from the $$^{10}$$B conversion layer in the detector prior to causing signals in the $$X$$ and $$Y$$ superconducting Nb nanowire meander lines. 478 keV prompt gamma rays emitted by $$^{7}$$Li nuclei from neutron-$$^{10}$$B reactions had negligible contribution to the simulated CB-KID images. Simulated neutron images of $$^{10}$$B dot arrays indicate that sub 10 $$mu$$m resolution imaging should be feasible with the current CB-KID design. The effect of the geometrical structure of CB-KID on the intrinsic detection efficiency was calculated from the simulations. An analytical equation was then developed to approximate this contribution to the detection efficiency. Detection efficiencies calculated in this study are upper bounds for the reality as the effects of detector temperature, the bias current, signal processing and dead-time losses were not taken into account. The modelling strategies employed in this study could be used to evaluate modifications to the CB-KID design prior to actual fabrication and testing, conveying a time and cost saving.


Repeatability and reproducibility of measurements of low dissolved radiocesium concentrations in freshwater using different pre-concentration methods

栗原 モモ*; 保高 徹生*; 青野 辰雄*; 芦川 信雄*; 海老名 裕之*; 飯島 健*; 石丸 圭*; 金井 羅門*; 苅部 甚一*; 近内 弥恵*; et al.

Journal of Radioanalytical and Nuclear Chemistry, 322(2), p.477 - 485, 2019/11

 被引用回数:0 パーセンタイル:100(Chemistry, Analytical)



Simulation study on the design of nondestructive measurement system using fast neutron direct interrogation method to nuclear materials in fuel debris

前田 亮; 古高 和禎; 呉田 昌俊; 大図 章; 米田 政夫; 藤 暢輔

Journal of Nuclear Science and Technology, 56(7), p.617 - 628, 2019/07

 被引用回数:1 パーセンタイル:53.3(Nuclear Science & Technology)

In order to measure the amount of nuclear materials in the fuel debris produced in the Fukushima Daiichi Nuclear Power Plant accident, we have designed a measurement system based on a Fast Neutron Direct Interrogation (FNDI) method. In particular, we have developed a fast response detector bank for fast neutron measurements by Monte Carlo simulations. The new bank has more than an order of magnitude faster response compared to the standard ones. We have also simulated the nondestructive measurements of the nuclear materials in homogeneously mixed fuel debris with various matrices which contain Stainless Steel (JIS SUS304), concrete, and various control-rod (CR) contents in the designed system. The results show that at least some types of the fissile materials in the debris can be measured by using the designed system.


Calculation of gamma and neutron emission characteristics emitted from fuel debris as a basis for determination of suitable detector system

Riyana, E. S.; 奥村 啓介; 寺島 顕一

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 4 Pages, 2019/05

Determination of fuel debris location and distribution inside primary containment vessel (PCV) of Fukushima Daiichi Nuclear Power Station is important to decide further decommissioning step and strategy. Past measurements not yet provide enough information to determine fuel debris location and its distribution inside PCV. To support further measurements effort, we simulate detector response inside PCV based on calculated photon and neutron emission spectrum produced from fuel debris. The Calculation result could be use as basis for determination of suitable spectrometer system or detector for search, localized, define fuel debris distributions and treatment of fuel debris.


Study of chemical etching conditions for alpha-particle detection and visualization using solid state nuclear track detectors

山田 椋平; 小田桐 大貴*; 岩岡 和輝*; 細田 正洋*; 床次 眞司*

Radiation Environment and Medicine, 8(1), p.21 - 25, 2019/02

固体飛跡検出器であるCR-39を用いたパッシブ型の測定器によってラドン・トロン及びその子孫核種を評価している。曝露後、CR-39は化学エッチング処理を行う必要がある。本研究では、この処理時間を短縮するためにCR-39の化学エッチング時間の短縮と、将来的な自動計数システムの導入を見据えたトラック直径(エッチピット直径)の拡大を検討した。最適なエッチング条件は、溶液濃度, 溶液温度及びエッチング時間を変えることによって決定した。その結果、最適条件(濃度, 温度, エッチング時間)は6M NaOH溶液, 75度, 10時間と決定された。これらの結果は、従来の化学エッチング時間の半分の時間で処理が完了することを示した。さらに、従来のトラック直径の拡大を考慮しなければ、より短いエッチング時間で処理を行うことが可能であることが示唆された。


Decreasing trend of ambient dose equivalent rates over a wide area in eastern Japan until 2016 evaluated by car-borne surveys using KURAMA systems

安藤 真樹; 三上 智; 津田 修一; 吉田 忠義; 松田 規宏; 斎藤 公明

Journal of Environmental Radioactivity, 192, p.385 - 398, 2018/12

 被引用回数:8 パーセンタイル:37.03(Environmental Sciences)



Measurement of ambient dose equivalent rates by walk survey around Fukushima Dai-ichi Nuclear Power Plant using KURAMA-II until 2016

安藤 真樹; 山本 英明*; 菅野 隆*; 斎藤 公明

Journal of Environmental Radioactivity, 190-191, p.111 - 121, 2018/10

 被引用回数:9 パーセンタイル:32.19(Environmental Sciences)



Development of a radiological characterization submersible ROV for use at Fukushima Daiichi

Nancekievill, M.*; Jones, A. R.*; Joyce, M. J.*; Lennox, B.*; Watson, S.*; 片倉 純一*; 奥村 啓介; 鎌田 創*; 加藤 道男*; 西村 和哉*

IEEE Transactions on Nuclear Science, 65(9), p.2565 - 2572, 2018/09

 被引用回数:5 パーセンタイル:18.88(Engineering, Electrical & Electronic)

福島第一原子力発電所の格納容器内に水没した燃料デブリを探査する技術の開発に貢献するため、小型の放射線検出器とソナーを搭載した遠隔水中ロボット(ROV)システムの開発を行っている。線量率モニタリングおよび$$gamma$$線分光法のための臭化セリウム(CeBr$$_{3}$$)シンチレータ検出器をROVに統合し、実験室および水中の両条件で$$^{137}$$Cs線源を用いて実験的に検証した。さらに、IMAGENEX 831Lソナーと組み合わせたROVは、水プール設備の底に置いた模擬燃料デブリの形状およびサイズを特徴付けることができた。


A Proposal of secure non-destructive detection system of nuclear materials in heavily shielded objects and interior investigation system

瀬谷 道夫; 羽島 良一*; 呉田 昌俊

Proceedings of INMM 58th Annual Meeting (Internet), 10 Pages, 2017/07



Reliability estimation of neutron resonance thermometry using tantalum and tungsten

甲斐 哲也; 廣井 孝介; Su, Y.; 篠原 武尚; Parker, J. D.*; 松本 吉弘*; 林田 洋寿*; 瀬川 麻里子; 中谷 健; 及川 健一; et al.

Physics Procedia, 88, p.306 - 313, 2017/06

 被引用回数:2 パーセンタイル:11.54

Neutron resonance thermometry, which measures material temperature by analyzing the Doppler broadening of a neutron resonance peak, is one of the applications of energy-resolved neutron imaging at RADEN of J-PARC. Although this technique is promising, advantages and disadvantages have not been discussed in practical applications. The authors measured neutron transmission rates of tantalum and tungsten foils in a heater chamber up to 300 degrees Celsius at RADEN. The energy-dependent neutron transmission rates with different statistics were obtained after the measurements by selecting arbitrary measuring intervals from one measurement, and the temperatures of the foils were estimated from those transmission rates with different statistics. The reliability of the neutron resonance thermometry with statistical accuracy, irradiation time and spatial resolution are discussed.


A Remote-operated system to map radiation dose in the Fukushima Daiichi primary containment vessel

Nancekievill, M.*; Jones, A. R.*; Joyce, M. J.*; Lennox, B.*; Watson, S.*; 片倉 純一*; 奥村 啓介; 鎌田 創*; 加藤 道男*; 西村 和哉*

Proceedings of 5th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA 2017) (USB Flash Drive), 6 Pages, 2017/06



Development of CdTe pixel detectors combined with an aluminum Schottky diode sensor and photon-counting ASICs

豊川 秀訓*; 佐治 超爾*; 川瀬 守弘*; Wu, S.*; 古川 行人*; 梶原 堅太郎*; 佐藤 真直*; 広野 等子*; 城 鮎美*; 菖蒲 敬久; et al.

Journal of Instrumentation (Internet), 12(1), p.C01044_1 - C01044_7, 2017/01

 被引用回数:1 パーセンタイル:88.48(Instruments & Instrumentation)

アルミニウムショットキーダイオードセンサとフォトンカウンティングASICsを組み合わせたCdTeピクセル検出器の開発を行っている。このハイブリッドピクセル検出器は、200マイクロメートル$$times$$200マイクロメートルのピクセルサイズで、19ミリメートル$$times$$20ミリメートルまたは38.2ミリメートル$$times$$40.2ミリメートルの面積で設計された。フォトンカウンティングASIC SP8-04F10Kは、プリアンプ,シェーパ, 3レベルのウィンドウタイプのディスクリミネータ、および各ピクセルが24ビットカウンタを備えている。そしてウィンドウコンパレータを用いてX線エネルギーを選択するフォトンカウンティングモードで精密に動作し、100$$times$$95ピクセルのシングルチップ検出器が20$$^{circ}$$Cで実現している。本研究では、本検出器の性能を評価するため、白色X線マイクロビーム実験のフィージビリティスタディを行った。珪素鋼試料に白色X線を照射し、照射位置を走査しながらラウエ回折を測定した。その結果、各位置で隣接する画像間の差を用いることで試料内の粒界の観察に成功した。


Neutron flux spectrum revealed by Nb-based current-biased kinetic inductance detector with a $$^{10}$$B conversion layer

宮嶋 茂之*; 宍戸 寛明*; 鳴神 吉人*; 吉岡 直人*; 藤巻 朗*; 日高 睦夫*; 及川 健一; 原田 正英; 奥 隆之; 新井 正敏*; et al.

Nuclear Instruments and Methods in Physics Research A, 842, p.71 - 75, 2017/01

 被引用回数:9 パーセンタイル:14.65(Instruments & Instrumentation)

We successfully derived the time-dependent flux of pulsed neutrons using a superconducting Nb-based current biased kinetic inductance detector (CB-KID) with a $$^{10}$$B conversion layer at Japan Proton Accelerator Research Complex. Our CB-KID is a meander line made of a 40-nm-thick Nb thin film with 1-$$mu$$m line width, which is covered with a 150-nm-thick $$^{10}$$B conversion layer. The detector works at a temperature below 4 K. The evaluated detection efficiency of the CB-KID in this experiment is 0.23% at the neutron energy of 25.4 meV. The time-dependent flux spectra of pulsed neutrons thus obtained are in good agreement with the results obtained by the Monte Carlo simulations.

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