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論文

Effect of sample density in prompt $$gamma$$-ray analysis

前田 亮; 瀬川 麻里子; 藤 暢輔; 遠藤 駿典; 中村 詔司; 木村 敦

Scientific Reports (Internet), 12(1), p.6287_1 - 6287_8, 2022/06

 被引用回数:1 パーセンタイル:0(Multidisciplinary Sciences)

A high-accuracy analytical method is broadly required to obtain reliable research results. Thus, prompt $$gamma$$-ray analysis (PGA), one of the most accurate non-destructive analytical methods, has been employed in various fields. However, the measurement accuracy of PGA is also known to degrade in hydrogenous samples. The degradation is caused by variation in the measurement sensitivity (counts per milligram) following the change in neutron energy due to scattering with hydrogen nucleus. Number of scatterings is well known to depend on the hydrogen content in a sample. However, considering multiple scatterings, hydrogen density, which has not been taken into account as yet, may also lead to the accuracy degradation. In this research, the effect of the hydrogen density in PGA is investigated by evaluating the measurement sensitivity of samples with the same hydrogen content and different densities. The results showed that the measurement sensitivity varies by more than 30% depending on the hydrogen density even at the same hydrogen content. The variation is a particularly serious problem for PGA requiring a few percent accuracy in most cases. Additionally, although the variation is apparently observed in hydrogenous samples, the similar phenomenon can occur in other nuclides with a large scattering cross section; it may affect nuclear cross-section measurements using neutrons in such fields as astrophysics and nuclear energy.

論文

Investigation of radioactive samples for neutron capture reaction measurements using energy-resolved neutron imaging

瀬川 麻里子; 藤 暢輔; 甲斐 哲也; 木村 敦; 中村 詔司

Annals of Nuclear Energy, 167, p.108828_1 - 108828_5, 2022/03

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

To obtain accurate analytical results via neutron-capture reactions, the effects of sample shapes must be considered. However, the estimations of the effects were difficult to verify in some cases such as sealed samples and valuable objects. In this study, the shape effects for sealed radioactive samples were estimated experimentally. The significant localization of the $$^{129}$$I sample was confirmed only by an energy-resolved neutron imaging. It is revealed that the shape effect was necessary to be corrected at the neutron resonance peaks. Consequently, we conclude that the energy-resolved neutron imaging will be quite effective to improve the analytical accuracy.

論文

Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV

遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.; 寺田 和司*; 明午 伸一郎; 藤 暢輔; 瀬川 麻里子; et al.

Journal of Nuclear Science and Technology, 59(3), p.318 - 333, 2022/03

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

In order to improve the accuracy of the cross-section and the resonance parameters of $$^{93}$$Nb, neutron capture and total cross-sections were measured using the J-PARC MLF ANNRI. The thermal-neutron capture cross-section was deduced as 0.97$$pm$$0.12 b. The resonance parameters of 11 resonances below 400 eV were determined from obtained capture cross-sections and transmission ratios by using the resonance analysis code, REFIT.

論文

Nondestructive quantitative analysis of difficult-to-measure radionuclides $$^{107}$$Pd and $$^{99}$$Tc

藤 暢輔; 瀬川 麻里子; 前田 亮; 常山 正幸*; 木村 敦; 中村 詔司; 遠藤 駿典; 海老原 充*

Analytical Chemistry, 93(28), p.9771 - 9777, 2021/07

 被引用回数:2 パーセンタイル:35(Chemistry, Analytical)

Considering the expanding demand for nuclear waste management of the spent nuclear fuel materials in near future, a non-destructive analytical scheme applicable to the most difficult-to-measure nuclide of $$^{107}$$Pd, which emits no decay gamma-rays and whose half-life is too long to be decayed out during a human lifetime, was designed. The scheme consists of a sophisticated instrument capable of the detection of gamma-rays by Ge detectors coupled with time-of-flight measurement of neutrons and a high-intensity pulsed neutron beam, and can simultaneously perform TOF-coupled prompt gamma-ray analysis (TOF-PGA) as well as PGA and NRCA. An analytical capability was evaluated by applying to simulated samples of the Tc-platinum group metals (Tc-PGMs) obtained by the group partitioning process of spent nuclear fuels, which contain not only $$^{107}$$Pd but also $$^{99}$$Tc and another difficult-to-measure fission product. It was confirmed that, although PGA and NRCA could accurately analyze both nuclides in individual single substances, only TOF-PGA can analyze $$^{107}$$Pd as well as $$^{99}$$Tc in the Tc-PGMs simulated sample. The TOF-PGA measurement technique can be widely used for the non-destructive analysis of $$^{107}$$Pd and $$^{99}$$Tc in nuclear wastes.

論文

Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC

川瀬 頌一郎*; 木村 敦; 原田 秀郎; 岩本 信之; 岩本 修; 中村 詔司; 瀬川 麻里子; 藤 暢輔

Journal of Nuclear Science and Technology, 58(7), p.764 - 786, 2021/07

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

The neutron capture cross sections of $$^{244}$$Cm and $$^{246}$$Cm were measured for the neutron energy range of 1-1000 eV via the neutron time-of-flight method with ANNRI at MLF of the J-PARC. The world's most intense neutron pulses from the Japan Spallation Neutron Source enable the accurate measurement of neutron capture cross sections. Besides, single-bunched neutron pulses allow the analysis in a higher neutron energy region than the previous measurement at ANNRI. The resonance analyses were performed up to 1000 eV by using a resonance shape analysis code REFIT. The spectra of prompt gamma-rays from neutron capture reactions of $$^{244}$$Cm and $$^{246}$$Cm were also obtained, and 43 and 10 prompt gamma-ray peaks from $$^{244}$$Cm(n,$$gamma$$) and $$^{246}$$Cm(n,$$gamma$$) reactions were newly observed, respectively.

論文

Feasibility study of PGAA for boride identification in simulated melted core materials

土川 雄介; 阿部 雄太; 大石 佑治*; 甲斐 哲也; 藤 暢輔; 瀬川 麻里子; 前田 亮; 木村 敦; 中村 詔司; 原田 正英; et al.

JPS Conference Proceedings (Internet), 33, p.011074_1 - 011074_6, 2021/03

福島原子力発電所の解体作業では、溶融した燃料棒に含まれるホウ素分布を事前に把握することが重要である。溶融燃料棒の模擬試験体を用意し、ホウ素やホウ化物の含有量を調査する研究が行われてきた。本研究では、その一環として中性子を用いたホウ素並びにホウ化物分布の測定技術開発を行った。ホウ素の中性子吸収に伴う即発ガンマ線を測定し、ホウ素量や二次元分布を測定した。また、n(B,$$alpha$$$$gamma$$)反応における478keV$$gamma$$線は、ホウ素の化合状態により、$$gamma$$線ピークの幅が変化することが知られている。このことを用い、特に溶融燃料棒周辺に存在することが予測されているZrBやFeBといったホウ化物の識別可能性について調査した。測定はJ-PARC/MLFのANNRI, NOBORU, RADENにて行った。これらの解析結果について報告する。

論文

Analytical method for the determination of $$^{211}$$At using an $$alpha$$-scintillation-camera system and thin-layer chromatography

瀬川 麻里子; 西中 一朗*; 藤 暢輔; 前田 亮

Journal of Radioanalytical and Nuclear Chemistry, 326(1), p.773 - 778, 2020/10

 被引用回数:1 パーセンタイル:18.46(Chemistry, Analytical)

$$^{211}$$At is a candidate nuclide for alpha-targeted therapy. In order to use $$^{211}$$At as a pharmaceutical, the radioactivity and chemical forms of generated $$^{211}$$At are the most fundamental specifications that need to be analyzed prior to its medical use. However, previous methods of separately measuring the radioactivity and chemical forms are not adaptable to the medical use of $$^{211}$$At because they cause a severe loss of $$^{211}$$At and do not analyze all the chemical forms of $$^{211}$$At. Therefore, a new analytical method for both the radioactivity and chemical forms of generated $$^{211}$$At is urgently needed. Accordingly, in this study, we developed an experimental system optimized to simultaneously analyze both the radioactivity and chemical forms of a $$^{211}$$At solution to significantly shorten the analysis time; we experimentally verified the accuracy and capabilities of this system at the Japan Atomic Energy Agency. The experiments confirmed that the present system could analyze the radioactivity and all the chemical forms of $$^{211}$$At with an uncertainty of approximately 5% in the region higher than 150 Bq and that it was 200 times more sensitive than the conventional method using an imaging technique with an X-ray imaging plate. As a result, a new method for analyzing the radioactivity and chemical forms of $$^{211}$$At was successfully established and this method will meet the demands for alpha-targeted therapy using $$^{211}$$At. This method will contribute to promoting the stable supply of the medical use of $$^{211}$$At in the near future.

論文

The Energy-resolved neutron imaging system, RADEN

篠原 武尚; 甲斐 哲也; 及川 健一; 中谷 健; 瀬川 麻里子; 廣井 孝介; Su, Y. H.; 大井 元貴; 原田 正英; 飯倉 寛; et al.

Review of Scientific Instruments, 91(4), p.043302_1 - 043302_20, 2020/04

 被引用回数:30 パーセンタイル:96(Instruments & Instrumentation)

The energy-resolved neutron imaging system, RADEN, has been installed at the pulsed neutron source in the Materials and Life Science Experimental Facility of the Japan Proton Accelerator Research Complex. In addition to conventional neutron radiography and tomography, RADEN, the world's first imaging beam-line at a pulsed neutron source, provides three main options for new, quantitative neutron imaging techniques: Bragg-edge imaging to visualize the spatial distribution of crystallographic information, resonance absorption imaging for elemental composition and temperature information, and polarized neutron imaging for magnetic field information. This paper describes the results of characterization studies of the neutronic performance and installed devices at RADEN and shows the results of several demonstration studies for pulsed neutron imaging.

論文

Feasibility study of two-dimensional neutron-resonance thermometry using molybdenum in 316 stainless-steel

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

Materials Research Proceedings, Vol.15, p.149 - 153, 2020/02

A two-dimensional thermometry technique based on neutron resonance reactions derives the temperature of specified elements in an object by analyzing the Doppler broadening of a neutron resonance measured by a time-analyzing neutron imaging-detector. This technique is expected to be one of the important applications of the energy-resolved neutron imaging system, RADEN, at J-PARC. The authors focused on molybdenum contained in 316 stainless-steel (with a weight fraction of 2-3 wt%). Energy-dependent transmitted neutrons were measured through a 3 mm thick 316 stainless-steel plate placed in a heater at temperatures between 23 and 500 degrees Celsius at RADEN using a gas-electron multiplier (GEM) detector. Thermal and cold neutrons were eliminated from the incident beam by a cadmium filter. The sample area within the neutron beam was 30 by 50 mm$$^2$$. The feasibility is discussed in the presentation.

論文

Neutron capture cross-section measurement and resolved resonance analysis of $$^{237}$$Np

Rovira, G.*; 片渕 竜也*; 登坂 健一*; 松浦 翔太*; 寺田 和司*; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之; 瀬川 麻里子; et al.

Journal of Nuclear Science and Technology, 57(1), p.24 - 39, 2020/01

 被引用回数:7 パーセンタイル:75.15(Nuclear Science & Technology)

The neutron capture cross-section of $$^{237}$$Np has been measured in the neutron energy region of 10 meV to 500 eV. A neutron time-of-flight method was employed using the NaI(Tl) spectrometer in the ANNRI beam-line at the Japanese Proton Accelerator Re-search Complex (J-PARC). The experimental capture yield was derived using the pulse-height weighting technique and an energy dependent cross-section was obtained relative to the incident neutron spectrum derived from a $$^{10}$$B(n, $$alpha$$)$$^{7}$$Li reaction yield. The absolute cross-section was determined by normalizing the results to JENDL-4.0 cross-section data at the first resonance of $$^{237}$$Np. The thermal cross-section was measured to be 177.6 $$pm$$ 3.8 b. The resolved resonance region was analyzed with the REFIT code.

論文

Characteristics of the 2012 model lithium-6 time-analyzer neutron detector (LiTA12) system as a high efficiency detector for resonance absorption imaging

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

Physica B; Condensed Matter, 551, p.496 - 500, 2018/12

 被引用回数:1 パーセンタイル:6.22(Physics, Condensed Matter)

The 2012 model lithium-6 time-analyzer neutron detector (LiTA12) system, based on a lithium glass scintillator and multi-anode photomultiplier tube, has the highest neutron efficiency among the detectors for pulsed neutron imaging together with a flexibility of the efficiency by changing the thickness of the lithium glass. The authors expect this detector system could become a main detector system for the energy-resolved neutron imaging system, RADEN, at J-PARC, and have started evaluation of the LiTA12 system. For example, spatial resolution for resonance absorption imaging was evaluated by using a line-pair pattern made by 3 micro meter thick gold on a quartz plate. Less than 1 mm width line pairs were resolved at an 8 Mcps neutron counting rate and around 5 eV neutron energy.

論文

Spatial resolution test targets made of gadolinium and gold for conventional and resonance neutron imaging

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

JPS Conference Proceedings (Internet), 22, p.011028_1 - 011028_8, 2018/11

We have fabricated and utilized spatial resolution test targets made of gadolinium and gold for conventional and resonance neutron imaging performed at RADEN, located at beam line BL22 of the J-PARC Materials and Life Science Experimental Facility (MLF). RADEN covers a broad energy range from cold neutrons to high-energy neutrons with energy of several tens keV and was designed to perform energy-resolved neutron imaging utilizing two-dimensional detectors combined with the accurate measurement of neutron energy by the time-of-flight method. The test targets were designed to verify the spatial resolution and image uniformity of two kinds of neutron detectors, counting-type detectors and camera-type detectors. In this presentation, we report the details of these two-dimensional test targets, and the results of demonstrations using the test targets with our neutron imaging detectors. This work was supported in part by the Photon and Quantum Basic Research Coordinated Development Program from the Ministry of Education, Culture, Sports, Science and Technology, Japan.

論文

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:3 パーセンタイル:81.95

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.

論文

Development of a three-dimensional computed tomography system using high-speed camera at a pulsed neutron source

瀬川 麻里子; 大井 元貴; 甲斐 哲也; 篠原 武尚; 佐藤 博隆*; 呉田 昌俊

JPS Conference Proceedings (Internet), 8, p.036006_1 - 036006_6, 2015/09

A neutron energy resolved three-dimensional (3D) imaging system with a high-speed video camera (CMOS, 1300 k frame/sec) and time-of-flight technique has been newly developed and installed at Japan Proton Accelerator Research Complex (J-PARC). The aim is to investigate a spatial distribution of several elements and crystals in various kinds of materials or substances more rapidly. The system allows to obtain TOF images consecutively resolved into narrow energy ranges in the pulsed neutron energy region from 0.01 to a few keV. The camera system was successfully demonstrated to obtain the reconstructed 3D images for Cu, Fe, Pb, and Polyethylene samples and the neutron energy dependence of the CT values, which are proportional to the total neutron cross sections. With use of the energy dependence of each CT values, it is possible to emphasize the selected materials, even if materials such as Cu and Fe have similar energy dependence of CT values. The results showed that this technique has the possibility to visualize material alternatively by choosing neutron energy and emphasize materials with use of the energy dependence of CT values.

論文

Development of a pulsed neutron three-dimensional imaging system using a highly sensitive image-intensifier at J-PARC

瀬川 麻里子; 大井 元貴; 甲斐 哲也; 篠原 武尚; 呉田 昌俊; 坂本 健作; 伊巻 正*

Nuclear Instruments and Methods in Physics Research A, 769, p.97 - 104, 2015/01

 被引用回数:1 パーセンタイル:10.52(Instruments & Instrumentation)

In order to realize neutron energy resolved three-dimensional (3D) imaging at resonance neutron energy region, a camera system coupled with a high sensitive and high frame-rate gating image-intensifier was developed. The resonance absorption 3D imaging was successfully demonstrated at pulsed neutron source of Japan Proton Accelerator Research Complex (J-PARC). The camera system allowed us to obtain a Time-of-flight (TOF) image of 2352 (W) $$times$$ 1726 (H) pixels resolved into a narrow energy range. The 3D images having enhanced contrast at corresponding resonance energy regions for cylindrical Au, Ta and In samples were reconstructed by "Convolution Filtered Back-Projection (FBP)" and "Maximum Likelihood Expectation Maximization (MLEM)" methods. And qualities of spatial resolutions in the depth direction were evaluated to be about 1 mm experimentally. The results obtained in the present experiments showed that the system could have the ability to adjust the practical use in the industrial field.

論文

中性子ビジュアルセンシング技術

呉田 昌俊; 瀬川 麻里子

ぶんせき, 2014(6), p.283 - 289, 2014/06

中性子線を利用して複合材料や機械部品等の内部を可視化し、記録した情報を分析することにより有意な物理量を測定する技術を中性子ビジュアルセンシング技術と呼ぶ。本稿では、技術の基礎と著者が研究開発した手法や装置を用いた応用事例について、次に大強度陽子加速器施設J-PARCを利用した最先端技術の研究開発の現状と応用について全体像を記し、最後に放射線利用装置開発のノウハウを企業による微量元素分析装置開発に生かし製品化に成功した事例を紹介する。

論文

Measurements of neutron capture cross section for $$^{207,208}$$Pb

瀬川 麻里子; 藤 暢輔; 原田 秀郎; 北谷 文人; 小泉 光生; 深堀 智生; 大島 真澄*; 岩本 信之; 岩本 修; 初川 雄一; et al.

AIP Conference Proceedings 1594, p.339 - 344, 2014/05

 被引用回数:0 パーセンタイル:0.02

Pb isotopes represent a sensitive test for models of $$s$$-process nucleosynthesis, since the decomposition of the complex abundance pattern in these mass regions is difficult to be accounted for by classical $$s$$-process model. Main neutron capture processes, the $$s$$- and $$r$$-processes, attribute to the origin of the isotopes in this mass region. As the aspects of neutron sources of the $$s$$-process, Gallino et al. reported that $$^{13}$$C($$alpha$$, n) neutron source which is burning radiatively at $$kT$$ = 8 keV play an important role on $$s$$-process nucleosynthesis. Hence, in the present study, an anti-Compton NaI(Tl) spectrometer and highly enriched samples are used to determine the $$gamma$$-ray energy spectra from the (n, $$gamma$$) reaction. This NaI(Tl) spectrometer makes it possible to detect the discrete $$gamma$$-ray from the reaction to the low-lying states in $$^{207,208}$$Pb. We give results both neuron capture cross sections for $$^{207,208}$$Pb to obtain the pulse height spectra using NaI(Tl) spectrometer with time of flight method in the wide neutron energy range from 10 to 100 keV. The Maxwellian averaged capture cross sections for $$^{207,208}$$Pb are determined in the astrophysical relevant energy region.

論文

Neutron resonance imaging of a Au-In-Cd alloy for the JSNS

大井 元貴; 勅使河原 誠; 甲斐 哲也; 原田 正英; 前川 藤夫; 二川 正敏; 橋本 英子*; 瀬川 麻里子; 呉田 昌俊; Tremsin, A.*; et al.

Physics Procedia, 43, p.337 - 342, 2013/04

 被引用回数:7 パーセンタイル:92.26

JSNSの新しいデカップラー材料として、Au-In-Cd合金が提案されている。本研究に先立ち、Au-In-Cd合金の製造を行い、予定通りの組成の合金製造に成功した。製造した合金組成は金74.9%、インジウム0.5%、カドミウム24.6%である。本研究では、中性子の共鳴吸収イメージングにより、製造した材料内の元素分布を測定し、各元素が合金内に均一に分布していることを確認する。カメラ型システムと、MCP検出器を用いることで、測定方法を検証する。結果として、中性子共鳴吸収を利用することで、合金内の元素を区別した透過画像を取得でき、元素分布が均一であることを確認した。

論文

New production routes for medical isotopes $$^{64}$$Cu and $$^{67}$$Cu using accelerator neutrons

金 政浩*; 永井 泰樹; 岩本 信之; 湊 太志; 岩本 修; 初川 雄一; 瀬川 麻里子; 原田 秀郎; 今野 力; 落合 謙太郎; et al.

Journal of the Physical Society of Japan, 82(3), p.034201_1 - 034201_8, 2013/03

 被引用回数:31 パーセンタイル:81.47(Physics, Multidisciplinary)

分子イメージングと核医学治療に期待されている放射性同位体$$^{64}$$Cuと$$^{67}$$Cuの生成断面積を14MeVの加速器中性子を用い測定した。この結果とZn同位体の断面積評価値を用いて、40MeVで5mAの重陽子ビームによる$$^{nat}$$C(d,n)反応からの速中性子を用いて生成される$$^{64}$$Cuと$$^{67}$$Cuの量を計算した。$$^{64}$$Cuの生成量は、12時間照射で175gの$$^{64}$$Znについて1.8テラベクレルであり、$$^{67}$$Cuの生成量は2日間の照射で、$$^{67}$$Zn(n,p)$$^{67}$$Cu反応では184g $$^{67}$$Znに対して249ギガベクレルであり、$$^{68}$$Zn(n,x)$$^{68}$$Cuでは186g $$^{68}$$Znに対して287ギガベクレルである。以上より、$$^{67}$$Cuの生成には、極微量不純物放射性同位体しか生成しない$$^{68}$$Zn(n,x)$$^{68}$$Cu反応を新しく提唱した。また、$$^{64}$$Cuの生成には、$$^{64}$$Zn(n,p)$$^{64}$$Cu反応が期待できる反応であることを示した。

論文

中性子イメージングの最新技術情報と自動車開発への応用

呉田 昌俊; 瀬川 麻里子

自動車技術会シンポジウムテキスト, No.9-11, p.24 - 29, 2012/01

中性子イメージング技術は、最先端の非破壊可視化・計測技術の一つである。本シンポジウムでは、可視化計測の基本原理、応用事例、J-PARCを利用したパルス中性子イメージングについて講演する。エンジンやデフへの応用例も含めて、高速度撮像イメージング、3次元や4次元CT、速度計測、最先端のパルス中性子イメージングに関して技術カタログ的に紹介する。

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