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論文

Demonstration of shape analysis of neutron resonance transmission spectrum measured with a laser-driven neutron source

小泉 光生; 伊藤 史哲*; Lee, J.; 弘中 浩太; 高橋 時音; 鈴木 敏*; 有川 安信*; 安部 勇輝*; Lan, Z.*; Wei, T.*; et al.

Scientific Reports (Internet), 14, p.21916_1 - 21916_9, 2024/09

 被引用回数:0

Laser-driven neutron sources (LDNSs) can generate strong short-pulse neutron beams, which are valuable for scientific studies and engineering applications. Neutron resonance transmission analysis (NRTA) is a nondestructive technique used for determining the areal density of each nuclide in a material sample using pulsed thermal and epithermal neutrons. Herein, we report the first successful NRTA performed using an LDNS driven by the Laser for Fast Ignition Experiment at the Institute of Laser Engineering, Osaka University. The key challenge was achieving a well-resolved resonance transmission spectrum for material analysis using an LDNS with a limited number of laser shots in the presence of strong background noise. We addressed this by employing a time-gated $$^{6}$$Li-glass scintillation neutron detector to measure the transmission spectra, reducing the impact of electromagnetic noise and neutron and gamma-ray flashes. Output waveforms were recorded for each laser shot and analyzed offline using a counting method. This approach yielded a spectrum with distinct resonances, which were attributed to $$^{115}$$In and $$^{109}$$Ag, as confirmed through neutron transmission simulation. The spectrum was analyzed using the least-square nuclear-resonance fitting program, REFIT, demonstrating the possibility of using an LDNS for nondestructive areal-density material characterization.

報告書

中性子共鳴イメージング解析コードRAIMマニュアル

長谷美 宏幸; 甲斐 哲也

JAEA-Testing 2024-001, 39 Pages, 2024/08

JAEA-Testing-2024-001.pdf:1.4MB

RAIM (Resonance Analysis code for neutron IMaging)は大強度陽子加速器施設J-PARCの物質・生命科学実験施設(MLF)などのパルス中性子源で測定した共鳴吸収スペクトルを解析し、試料の原子核の密度や温度などの情報を求める解析コードである。RAIMは中性子のパルス関数と断面積データをもとにした共鳴吸収関数の畳み込み計算によりパルス中性子源で測定される共鳴吸収スペクトルを再現し、測定で得られた共鳴吸収スペクトルデータに対してフィッティングを行うことで、試料に含まれる特定の元素の密度や温度を求めることができる。また、RAIMは計算設定のパラメータを極力少なくすることや、2次元検出器で測定した数多くのスペクトルを一括で処理するスクリプトを用意するなど、共鳴イメージングデータを容易に解析することを念頭に開発されている。本書はRAIMの計算機へのインストール方法および共鳴吸収スペクトルのシミュレーションと測定データへのフィッティング方法について説明するマニュアルである。

論文

Study on neutron beam pulse width dependence in the nuclear fuel measurement by the neutron resonance transmission analysis

北谷 文人; 土屋 晴文; 藤 暢輔; 堀 順一*; 佐野 忠史*; 高橋 佳之*; 中島 健*

KURRI Progress Report 2017, P. 99, 2018/08

As a non-destructive analytical technique for nuclear material in the field of nuclear security and nuclear nonproliferation, a neutron resonance transmission analysis (NRTA) attracts attention of researchers. It is important to downsize a NRTA system when it is deployed at various facilities. For this aim, we have developed a compact NRTA system which utilizes a D-T neutron generator. Its pulse width of 10$$mu$$s is much longer than that of a large electron beam accelerator. It is necessary to understand the influence of pulse widths on the NRTA measurement. Therefore, we conducted the experiments of the simulated nuclear fuel pin samples to evaluate how the NRTA measurement is influenced by the pulse width of neutron beam. Experiments were performed in Kyoto University. The simulated fuel pellet sample was made from metallic powders of Ag (around 1%) and Al (around 99%). The energy of the irradiation neutron is determined by a Time of Flight technique. We used three pulse widths of the neutron beam of 0.1, 1 and 4 $$mu$$s. A resonance dip of $$^{108}$$Ag at 5.19 eV is observed in the all spectra. And the dip of the TOF spectrum shifts towards low energy, with pulse width changed to a longer one. In this work, we confirmed that neutron pulse width affected the NRTA measurement of the fuel pin sample. On the basis of this work, we will be able to quantify the effects of long-pulse width in a resonance analysis.

論文

Neutron resonance transmission analysis for measurement of nuclear materials in nuclear fuel

土屋 晴文; 北谷 文人; 藤 暢輔; Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*

Proceedings of INMM 59th Annual Meeting (Internet), 6 Pages, 2018/07

In fields of nuclear safeguards and nuclear security, non-destructive assay (NDA) techniques are needed in order to quantify special nuclear materials (SNMs) in nuclear fuels. Among those techniques, active NDA ones would be preferable to passive ones. One candidate of active NDA techniques is neutron resonance transmission analysis (NRTA). In fact, experiments done at GELINA have shown that NRTA has high potential enough to quantify SNMs in complex materials. Currently, such a NRTA system requires a large electron accelerator facility to generate intense neutron sources. In other words, it is very difficult to perform NRTA at various facilities that need to measure SNMs. Thus, downsizing a NRTA system would be one solution of its difficulty. In order to realize a compact NRTA system, we develop a prototype with a D-T neutron generator that has a pulse width of 10 $$mu$$s. For this aim, numerical calculations to optimize the compact NRTA system were done. In addition, NRTA measurements with simulated fuel pins were made at neutron time-of-flight facilities such as GELINA. In this presentation, we present results of the numerical calculations and the experimental results. On the basis of those results we discuss a future prospect of a compact NRTA system that would be applicable to SNM quantification. This research was implemented under the subsidiary for nuclear security promotion of MEXT.

論文

Influence of the neutron transport tube on neutron resonance densitometry

北谷 文人; 土屋 晴文; 小泉 光生; 高峰 潤; 堀 順一*; 佐野 忠史*

EPJ Web of Conferences, 146, p.09032_1 - 09032_3, 2017/09

 被引用回数:0 パーセンタイル:0.00(Nuclear Science & Technology)

The use of a short flight path is effective in the neutron resonance analysis. On the other hand, such a short path would reduce a time resolution in Time-Of-Flight (TOF) measurements. In order to investigate the effect of neutron flight-path length, we carried out Neutron Resonance Transmission Analysis (NRTA) experiments with a short neutron flight path at the Kyoto University Research Reactor Institute - Linear Accelerator (KURRI-LINAC). In measurements of Neutron Resonance Densitometry, the quantity of nuclear materials is determined from TOF spectra obtained in the neutron energy range below 30 eV. Performing NRTA experiments with a 7-m flight path at KURRI-LINAC, we examined effects of flight path and pulse width on a TOF spectrum. A resonance dip of $$^{183}$$W at 27 eV in a TOF spectrum was successfully observed with an electron pulse width less than 2 $$mu$$s. In this presentation, we will discuss importance of the pulse width and short flight path to study design of a compact TOF facility to quantify nuclear materials.

論文

Generalized analysis method for neutron resonance transmission analysis

原田 秀郎; 木村 敦; 北谷 文人; 小泉 光生; 土屋 晴文; Becker, B.*; Kopecky, S.*; Schillebeeckx, P.*

Journal of Nuclear Science and Technology, 52(6), p.837 - 843, 2015/06

 被引用回数:3 パーセンタイル:24.66(Nuclear Science & Technology)

Neutron resonance densitometry (NRD) is a non-destructive analysis method, which can be applied to quantify special nuclear materials (SNM) in small particle-like debris of melted fuel that is formed in severe accidents of nuclear reactors such as the Fukushima Daiichi Nuclear Power Plants. NRD uses neutron resonance transmission analysis (NRTA) to quantify SNM and neutron resonance capture analysis (NRCA) to identify matrix materials and impurities. In order to generalize NRD for the characterization of arbitrary-shaped thick materials, a generalized method to analyze NRTA data has been developed. The method has been applied on data resulting from transmission through non-uniform thick samples with varying areal density of SNM up to 0.253 at/b ($$approx$$100 g/cm$$^{2}$$). The investigation shows that NRD could be used to quantify SNM in not only uniform samples made of small particle-like debris but also non-uniform samples made of large rock-like debris with high accuracy by utilizing the generalized analysis method for NRTA.

論文

JAEA-ISCN development programs of advanced NDA technologies of nuclear material

瀬谷 道夫; 小林 直樹; 直井 洋介; 羽島 良一; 曽山 和彦; 呉田 昌俊; 中村 仁宣; 原田 秀郎

Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03

原子力機構では、2011年度より次の3つのプログラムからなる先進核物質非破壊測定技術の基礎開発を実施している。(1)レーザー・コンプトン散乱$$gamma$$線(大強度単色$$gamma$$線)を使う核共鳴蛍光NDA技術開発、(2)ZnS/B$$_{2}$$O$$_{3}$$セラミックシンチレータによる中性子検出技術開発、(3)中性子共鳴透過分析(NRTA)及び中性子共鳴捕獲分析(NRCA)による中性子濃度分析法(NRD)技術開発。これらのプログラムは2014年度に終了する予定であり、2015年2-3月に実証試験を行う予定である。

口頭

Study of sample shape effects on neutron resonance transmission analysis

Ma, F.; 土屋 晴文; 北谷 文人

no journal, , 

Neutron resonance transmission analysis (NRTA) is a non-destructive assay technique and has a potential to evaluate the amount of special nuclear materials in nuclear fuels such as fuel debris and spent fuel. Those fuels, especially debris would have an irregular shape. It is expected that such an irregular shape affects NRTA measurements. In order to study how a sample shape affects measurements of NRTA, experiments with a Cu-bar sample with different rotation angles were done at a neutron Time-Of-Flight (TOF) facility GELINA (Belgium). A resonance analysis code Refit was used to analyze measured transmission spectra for individual rotation angles. It was found that the experimental transmission was able to be well fitted by considering the effect of hole-fraction and irregularity. This research was implemented under the subsidiary for nuclear security promotion of MEXT.

口頭

Characterization of nuclear material by neutron resonance transmission analysis

Schillebeeckx, P.*; Alaerts, G.*; Becker, B.*; Paradela, C.*; Heyse, J.*; Kopecky, S.*; Vendelbo, D.*; Wynants, R.*; 原田 秀郎; 北谷 文人; et al.

no journal, , 

中性子共鳴反応を利用して非破壊で試料を分析する手法に、中性子共鳴透過分析法(NRTA)がある。NRTAは中性子を試料に照射し、透過してくる中性子を計測することで試料を分析する。我々はJRC-IRMM(共同研究センター/標準物質・測定研究所)の中性子飛行時間施設GELINAにおいて、核物質の特性を評価するためNRTAの研究開発を行っている。その一環として、過酷事故で発生が予測される粒子状溶融燃料デブリに含まれる核物質の定量にNRTAを適用することを目的とした開発に取り組んできた。その開発の中で、デブリ中の核物質の定量精度が中性子吸収材のボロン($$^{10}$$B)の存在量やデブリのさまざまな形や大きさに強く影響を受けることがわかった。こうしたデブリに特徴的な性質に対処するため、解析手法の改良やモデルの開発を行ってきた。本発表では、開発した解析手法やモデルの妥当性を検討するためGELINAで実施したNRTA実験の結果について報告し、中性子吸収材の存在下においても、NRTAでは2%以下の精度で核分裂性物質の量を導出できることを示す。

口頭

Application of nuclear photonics for nuclear non-proliferation and security

小泉 光生; Lee, J.; 伊藤 史哲*; 高橋 時音; 鈴木 敏*; Omer, M.*; 瀬谷 道夫*; 羽島 良一; 静間 俊行; 余語 覚文*; et al.

no journal, , 

Along with the global increase of use of nuclear materials (NMs), growing requirements are development for new effective characterization methods for nuclear material accountancy and technologies to cope with the threat of nuclear terrorism. Non-destructive Assay (NDA) methods are an efficient, quick, and remote way to detect and quantify nuclear materials (NMs). Passive NDA techniques, which are based on radiation measurement, are conventionally used in accountancy for quantification of NMs and in security for detection and identification of NMs. However, they could not be applied to an object with strong radioactivity or in shielding materials. Active NDA techniques are, therefore, considered to be a breakthrough technique to measure such NMs samples by utilizing interrogation particles (such as photons and neutrons). Induced signals by the incident particles (for example, transmitted neutrons) are measured to deduce sample properties. This report overviews two research programs that utilize nuclear photonics technologies for nuclear non-proliferation and security. The research programs carried out by JAEA under collaborations are supported by MEXT (the Ministry of Education, Culture, Sports, Science and Technology of the Japanese government) under the subsidy for "promotion of strengthening nuclear security and the like".

口頭

High-speed atomic thermometer using single shot of laser-driven neutron pulse

Lan, Z.*; 余語 覚文*; 早川 岳人*; Wei, T.*; 加美山 隆*; 佐藤 博隆*; 有川 安信*; Mirfayzi, R.*; 小泉 光生; 安部 勇輝*; et al.

no journal, , 

Neutron resonance diagnosis technology has been developed worldwide for over ten years. By employing neutron beams with high transmittance, it is possible to measure the resonance spectral of samples in the neutron beam-line. We developed a new approach to generate short pulse epithermal neutron beams using relativistic intensity laser for the neutron resonance spectral diagnosis, which is known as Laser-Driven Epithermal Neutron Source (LDENS). Benefit from highly focused laser, the LDENS can provide high temporal accuracy with a compact volume of the source. Therefore, the minimal change of neutron resonance peaks caused by Doppler broadening effect of atom temperature could be detected via single pulse of LDENS. In experiment, we measured resonance at 4.28eV of a 0,1mm Ta plate with serial temperature points (300K-600K) and another resonance at 5.18eV of an Ag plate was recorded as a reference of the neutron signal. The experimental data shows the feasibility of isotope-discriminating atomic thermometer using a single shot of LDENS. More results will be reported in the presentation.

口頭

Nuclear thermometer using single pulse of laser-driven neutron source

Lan, Z.*; Wei, T.*; 早川 岳人*; 加美山 隆*; 佐藤 博隆*; 有川 安信*; Mirfayzi, S. R.*; 小泉 光生; 安部 勇輝*; Morace, A.*; et al.

no journal, , 

A Laser-Driven Neutron Source (LDNS) is a novel neutron that provides neutron beam of ultra-short pulse duration and high flux. This technique would be useful for neutron resonance non-destructive diagnosis application. A demonstration experiment was carried out using an LDNS developed for the LFEX laser of Institute of Laser Engineering, Osaka University. A neutron resonance spectrum was observed with a single laser shot. The technique can be used as a "nuclear thermometer" because the resonance shape is broadened as a function of the sample material temperature.

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