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論文

Delayed $$gamma$$-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

小泉 光生; Rossi, F.; Rodriguez, D.; 高峰 潤; 瀬谷 道夫; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EPJ Web of Conferences, 146, p.09018_1 - 09018_4, 2017/09

 被引用回数:3 パーセンタイル:86.61

Along with the global increase of applications using nuclear materials (NM), the requirements to nuclear security and safeguards for the development of effective characterization methods are growing. Mass verification of NM of low radioactivity is performed using passive non-destructive analysis (NDA) techniques whereas destructive analysis (DA) techniques are applied for accurate analysis of nuclide composition. In addition to the characterization by passive NDA, a sample can be further characterized by active NDA techniques. An active neutron NDA system equipped with a pulsed neutron generator is currently under development for studies of NDA methods. Among the methods DGS uses the detection of decay $$gamma$$-rays from fission products (FP) to determine ratios of fissile nuclides present in the sample. A proper evaluation of such $$gamma$$-ray spectra requires integration of nuclear data such as fission cross-sections, fission yields, half-lives, decay chain patterns, and decay $$gamma$$-ray emission probabilities. The development of the DGS technique includes experimental verification of some nuclear data of fissile materials, as well as development of the device. This presentation will be a brief introduction of the active neutron NDA project and an explanation of the DGS development program.

論文

LaBr$$_3$$ $$gamma$$-ray spectrometer for detecting $$^{10}$$B in debris of melted nuclear fuel

小泉 光生; 土屋 晴文; 北谷 文人; 原田 秀郎; Heyse, J.*; Kopecky, S.*; Mondelaers, W.*; Paradela, C.*; Schillebeeckx, P.*

Nuclear Instruments and Methods in Physics Research A, 837, p.153 - 160, 2016/11

 被引用回数:1 パーセンタイル:19.85(Instruments & Instrumentation)

Neutron Resonance Densitometry (NRD) has been proposed as a non-destructive analytical method for quantifying Special Nuclear Material (SNM) in the rock- and particle-like debris that is to be removed from the Fukushima Daiichi Nuclear Power Plant. The method is based on Neutron Resonance Transmission Analysis (NRTA) and Neutron Resonance Capture Analysis combined with Prompt Gamma Ray Analysis (NRCA/PGA). Although quantification of SNM will predominantly rely on NRTA, this will be hampered by the presence of strong neutron-absorbing matrix materials, in particular $$^{10}$$B. Results obtained with NRCA/PGA are used to improve the interpretation of NRTA data. Prompt $$gamma$$-rays originating from the $$^{10}$$B(n, $$alphagamma$$) reaction are used to assess the amount of $$^{10}$$B. The 478 keV $$gamma$$-rays from $$^{10}$$B, however, need to be measured under a high-radiation environment, especially from $$^{137}$$Cs. In order to meet this requirement, we have developed a well-shaped $$gamma$$-ray spectrometer consisting of a cylindrical and four rectangular cuboid LaBr$$_3$$ scintillators, and a fast data acquisition system.

論文

核不拡散用アクティブ中性子非破壊測定技術の開発,4; 遅発ガンマ線分光; 実験研究計画

小泉 光生; Heyse, J.*; Mondelaers, W.*; Paradela, C.*; Pedersen, B.*; Schillebeeckx, P.*; 瀬谷 道夫; Rodriguez, D.; 高峰 潤

核物質管理学会(INMM)日本支部第36回年次大会論文集(インターネット), 6 Pages, 2015/12

核分裂生成物の構成(分布)は、元となる核分裂性核種と照射中性子エネルギーにより異なってくる。それゆえ、核分裂生成物収率の違いによる遅発$$gamma$$線(DG)スペクトルの違いから、核分裂性核種($$^{235}$$U, $$^{239}$$Pu及び$$^{241}$$Pu)の比が求められる。このDGS法プロジェクトは、核データの確認と改良を行いつつ実施する測定システムに関する研究開発である。実験に関しては、中性子源と核物質が取り扱えるITU/Ispra(イタリア), IRMM(ベルギー),京都大学研究用原子炉(熊取)などの施設を用いて実施する予定である。本発表では、現在計画しているDGS法の開発実験について報告する。

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:4 パーセンタイル:26.04(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

NRDの開発,1;中性共鳴濃度分析法のためのLaBr$$_{3}$$シンチレーション検出装置の開発

小泉 光生; 土屋 晴文; 北谷 文人; 原田 秀郎; 高峰 潤; 呉田 昌俊; 瀬谷 道夫; 木村 敦; 飯村 秀紀; Becker, B.*; et al.

核物質管理学会(INMM)日本支部第35回年次大会論文集(インターネット), 8 Pages, 2015/01

粒子状デブリ中の核物質を定量するため、中性子共鳴濃度分析法(neutron resonance densitometry: NRD)を開発している。これは、中性子共鳴透過分析法(NRTA)と、中性子共鳴捕獲分析法(NRCA)または即発$$gamma$$線分析法(PGA)の2つの手法を組み合わせたものである。NRCA/PGAは、NRTAでは測定が難しい混入物の同定を行う。中性子捕獲$$gamma$$線を測定するために、LaBr$$_{3}$$検出器で構成されるスペクトロメータを開発している。導入したデータ収集系は、500kイベント/秒の信号を8チャンネルで扱うことができる。本講演では、NRDの研究開発状況ならびにスペクトロメータシステムの開発状況について発表する。

論文

Neutron resonance spectroscopy for the characterization of materials and objects

Schillebeeckx, P.*; Becker, B.*; 原田 秀郎; Kopecky, S.*

Landolt-B$"o$rnstein Group 1, Vol.26; Numerical Data and Functional Relationships in Science and Technology, Subv.A; Neutron Resonance Parameters, p.4 - 52, 2015/00

中性子と原子核が反応する確率は、入射中性子のエネルギーに大きく依存し、多くの原子核で中性子共鳴が現れる。この性質を利用した非破壊分析法として、中性子共鳴透過分析法と中性子共鳴捕獲$$gamma$$線分光法がある。本報告では、各分析法の原理を解説すると共に、両手法の利点を組み合わせた新たな非破壊分析法として開発を進めている中性子共鳴濃度分析法について解説する。

論文

Recent progress in research and development in neutron resonance densitometry (NRD) for quantification of nuclear materials in particle-like debris

小泉 光生; 北谷 文人; 土屋 晴文; 原田 秀郎; 高峰 潤; 呉田 昌俊; 飯村 秀紀; 瀬谷 道夫; Becker, B.*; Kopecky, S.*; et al.

Nuclear Back-end and Transmutation Technology for Waste Disposal, p.13 - 20, 2015/00

溶融燃料中の核物質の計量管理するための技術として、中性子共鳴濃度分析法(Neutron Resonance Densitometry (NRD))を提案している。この手法は、Neutron Resonance Transmission Analysis(NRTA)とNeutron Resonance Capture Analysis (NRCA)もしくはPrompt Gamma ray Analysis (PGA)の2つの手法を組み合わせたもので、パルス中性子源を装備した飛行時間(TOF)測定装置を用いる。この測定法を確立するために、検出器の開発を進めるとともに、EC-JRC-IRMMのGELINA TOF実験施設で、共同研究を進めている。研究進捗について、総括的に報告する。

論文

Thickness and mixed sample effects on areal density measurement with NRTA for particle like debris of melted fuel

土屋 晴文; 原田 秀郎; 小泉 光生; 北谷 文人; 高峰 潤; 呉田 昌俊; 飯村 秀紀; 木村 敦; Becker, B.*; Kopecky, S.*; et al.

Proceedings of INMM 55th Annual Meeting (Internet), 6 Pages, 2014/07

Neutron resonance densitometry (NRD) is based on a combination of neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA). This technique is a non-destructive method to quantify nuclear materials in particle-like debris of melted fuel that is generated by a severe accident like the one at the Fukushima Daiichi Nuclear Power Plant. To verify the effectiveness of NRD, the Japan Atomic Energy Agency (JAEA) and the Joint Research Center, Institute for Reference Materials and Measurements (EC-JRC-IRMM) started collaboration in 2012. One of the main objectives of this collaboration is to quantitatively investigate all uncertainty components on results of NRD measurements. Clearly, systematic effects due to the characteristics of samples such as the sample inhomogeneity, presence of impurities, radioactivity and temperature have a strong impact on the accuracy. To study the uncertainty due to the sample characteristics, NRTA and NRCA experiments are in progress at the time-of-flight facility GELINA (Geel Electron LINear Accelerator) of the EC-JRC-IRMM. In this presentation, we show results considering mixed sample effect on NRTA measurements. Data are analyzed with the resonance shape analysis code REFIT to derive the elemental composition of the sample and the areal density of the main components. In addition the effect of neutron absorbing matrix material will be discussed.

論文

Developments of a LaBr$$_3$$ scintillation detector system for neutron resonance densitometry (NRD)

小泉 光生; 土屋 晴文; 北谷 文人; 原田 秀郎; 高峰 潤; 呉田 昌俊; 瀬谷 道夫; 木村 敦; 飯村 秀紀; Becker, B.*; et al.

Proceedings of INMM 55th Annual Meeting (Internet), 7 Pages, 2014/07

Neutron resonance densitometry (NRD) has been proposed as a method to quantify the amount of special nuclear materials in particle-like debris of melted fuel. The requirements of a $$gamma$$-ray detector system for the NRD measurements are: (1) good energy resolution to identify elements (2) fast response not to be suffocated by the radiation from debris samples and (3) good signal to noise ratio. The quantification of $$^{10}$$B is considered to be the most important for NRD because of its very large neutron cross-sections. However, the Compton peak of the $$gamma$$ rays from $$^{137}$$Cs, which is probably the strongest radioactivity in debris, overlaps the $$^{10}$$B $$gamma$$ peak; and it makes the measurements difficult. We, therefore, designed a well-type LaBr$$_{3}$$ scintillation spectrometer to reduce the Compton peak. The progress of the research and development of the spectrometer is reported.

論文

Development of neutron resonance densitometry

原田 秀郎; Schillebeeckx, P.*; 土屋 晴文; 北谷 文人; 小泉 光生; 高峰 潤; 呉田 昌俊; 飯村 秀紀; 木村 敦; 瀬谷 道夫; et al.

Proceedings of INMM 55th Annual Meeting (Internet), 8 Pages, 2014/07

Neutron resonance densitometry (NRD) has been developed to quantify nuclear materials in particle-like debris of melted fuel formed in severe accidents of nuclear reactors such as Fukushima Daiichi Nuclear Power Plants. NRD is a method combining NRTA (neutron resonance transmission analysis) and NRCA (neutron resonance capture analysis). It relies on neutron TOF technique using a pulsed white neutron source. A specially designed $$gamma$$-ray spectrometer for NRCA has been developed for the characterization of contamination materials mixed with nuclear fuel materials. Achievable accuracy is studied based on Monte Carlo simulations and experimental data measured at the time-of-flight facility GELINA of the EC-JRC-IRMM. Analysis method of NRTA for particle-like debris has been developed by adding a function in a resonance analysis code REFIT. In this contribution, these achievements on NRD for the characterization of nuclear materials mixed with highly radioactive nuclides are reviewed, and its applicability is discussed.

論文

Neutron resonance densitometry for particle-like debris of melted fuel

原田 秀郎; 北谷 文人; 小泉 光生; 高峰 潤; 呉田 昌俊; 土屋 晴文; 飯村 秀紀; 瀬谷 道夫; Becker, B.*; Kopecky, S.*; et al.

Nuclear Data Sheets, 118, p.502 - 504, 2014/04

 被引用回数:4 パーセンタイル:33.13(Physics, Nuclear)

Feasibility study of neutron resonance densitometry (NRD) has been started to quantify of nuclear materials in particle-like debris of melted fuel formed in severe accidents of nuclear reactor such as Fukushima Daiichi Nuclear Power Plants. The NRD here is a combined method of NRTA (neutron resonance transmission analysis) and NRCA (neutron resonance capture analysis) using a pulsed neutron generator and TOF (time of flight) measurement. The presentation includes the proposed compact NRD system, the spectrometer design for NRCA using LaBr$$_{3}$$ detectors by Monte Carlo simulations, and analytical studies on achievable accuracies. The experimental results using particle-like Cu samples measured at the GELINA facility in IRMM are also shown in comparison with analytical studies. Required nuclear data for the NRD will be also discussed.

論文

Sample thickness effect on nuclear material quantification with NRTA for particle like debris of melted fuel

土屋 晴文; 原田 秀郎; 小泉 光生; 北谷 文人; 高峰 潤; 呉田 昌俊; 飯村 秀紀; Becker, B.*; Kopecky, S.*; Kauwenberghs, K.*; et al.

Proceedings of INMM 54th Annual Meeting (CD-ROM), 6 Pages, 2013/07

Neutron resonance densitometry (NRD) is based on a combination of neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA). This non-destructive technique is considered for the quantification of nuclear materials in samples of melted fuel that will be removed from the Fukushima Daiichi Nuclear Power Plant. However, NRD has never been applied for measurements of melted fuel, and the measurements are considered to be difficult because of the characteristics of the samples. To verify the effectiveness of NRD, all components having an impact on the results have to be investigated. The uncertainty of the result is strongly influenced by the characteristics of the sample, in particular the sample inhomogeneity, particle size, presence of neutron absorbing impurities, radioactivity and temperature. To estimate the impact of the sample characteristics, JAEA and JRC-IRMM have started a collaboration. Within this collaboration experiments are in progress at the Time-Of-Flight facility of the EC-JRC-IRMM. In this presentation, results of neutron transmission measurements on Cu samples with different thicknesses at a 25-m flight path are reported. The data, which are analyzed with a resonance shape analysis code REFIT, are used to verify the effect of the particle size and the presence of neutron absorbing impurities. Some of the results are also used to validate data obtained by Monte Carlo simulations.

論文

Recent progress in research and development on the neutron resonance densitometry for particle-like debris of melted fuel

原田 秀郎; 北谷 文人; 小泉 光生; 土屋 晴文; 高峰 潤; 呉田 昌俊; 飯村 秀紀; 瀬谷 道夫; Becker, B.*; Kopecky, S.*; et al.

Proceedings of INMM 54th Annual Meeting (CD-ROM), 10 Pages, 2013/07

粒子状溶融燃料に含有される核燃料を計量するために機構が開発を進めている中性子共鳴濃度分析法の技術開発の進捗について、測定原理の他、含有されるボロン等の不純物を分析するために特別に設計した$$gamma$$線検出器の評価、IRMMのパルス中性子発生施設GELINAで実施した試験研究の成果、及びプロトタイプ装置の設計を含め、総括的に報告する。

論文

Contribution of the JRC to the development of neutron resonance densitometry to characterize melted fuel from severe accidents

Schillebeeckx, P.*; Becker, B.*; Emiliani, F.*; Kopecky, S.*; Kauwenberghs, K.*; Moens, A.*; Mondelaers, W.*; Sibbens, G.*; 原田 秀郎; 北谷 文人; et al.

Proceedings of INMM 54th Annual Meeting (CD-ROM), 7 Pages, 2013/07

JAEA and EC-JRC started a collaboration to study Neutron Resonance Densitometry (NRD) as a method for the characterization of melted fuel formed in nuclear accidents. NRD is based on a combination of Neutron Resonance Transmission Analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA). In this presentation, the contribution of the EC-JRC-IRMM to the project is discussed. Within the project the GELINA facility will be used to validate the method and perform tests on calibration and test samples. In a first exercise the test samples will not contain actinides, however, they will contain nuclides having similar characteristics as the melted fuel for NRCA and NRTA. These samples will be produced and characterized at dedicated laboratories of our institute. To study the impact of the sample characteristics, in particular the particle size distribution of powder samples, various analytic models are compared. In addition stochastic simulations are used to select a specific model and to estimate the uncertainties introduced by the model. The stochastic model is also used to verify bias effects due to sample properties. The results of the simulations are verified by measurements at GELINA. In addition, the data reduction and analysis procedures will be adapted such that they can be used for in-field application of NRD. The changes required for NRD applications are discussed.

論文

Proposal of neutron resonance densitometry for particle like debris of melted fuel using NRTA and NRCA

原田 秀郎; 北谷 文人; 小泉 光生; 土屋 晴文; 高峰 潤; 呉田 昌俊; 飯村 秀紀; 瀬谷 道夫; Becker, B.*; Kopecky, S.*; et al.

Proceedings of 35th ESARDA Annual Meeting (Internet), 6 Pages, 2013/05

福島第一原子力発電所のような原子炉事故で発生すると考えられる粒子状溶融燃料中の核物質量を精度よく非破壊で計量するため、パルス中性子源を利用した中性子共鳴濃度分析法(Neutron Resonance Densitometry: NRD)を提案した。NRDは、中性子共鳴透過分析法(Neutron Resonance Transmission Analysis: NRTA)と中性子共鳴捕獲分析法(Neutron Resonance Capture Analysis: NRCA)を組合せた分析法である。本手法の分析原理、予備解析による測定精度及び開発計画について講演する。

論文

Promising NDA technologies for material accountancy of nuclear material in debris of melted fuel of Fukushima-Daiichi NPP

瀬谷 道夫; 原田 秀郎; 北谷 文人; 小泉 光生; 土屋 晴文; 羽島 良一; 早川 岳人; 静間 俊行; Angell, C.; Bolind, A.

Proceedings of 35th ESARDA Annual Meeting (Internet), 9 Pages, 2013/05

原子力機構がその基礎的な技術の実証を行っている、福島第一原子力発電所の溶融燃料中核物質計量管理のための有望な2つのNDA技術について、このセッションのイントロとして発表する。その一つは、粒子状デブリを対象とする中性子共鳴濃度分析法で、これは中性子飛行時間分析を使用する中性子共鳴透過分析法と中性子共鳴捕獲分析法をベースとする方法である。原子力機構とJRC-IRMMは2012年5月からこの方法に関する共同研究を実施している。この論文では、中性子共鳴濃度分析法について粗く紹介するが、このセッションの他の論文ではそれについて詳しく紹介する。もう一つは、レーザー・コンプトン散乱$$gamma$$線(LCS-$$gamma$$)を用いて切出し形状、小石状の溶融燃料デブリ中の核物質を分析する方法である。ここでは、LCS-$$gamma$$による核共鳴蛍光反応を利用する方法の溶融燃料デブリへの適用について粗く紹介する。このセッションの最後の2編では、エネルギー回収型リニアック(ERL)とレーザー蓄積装置をベースとする大強度の単色エネルギー$$gamma$$線発生実証と測定法について詳しく紹介する。

論文

Particle size inhomogeneity effect on neutron resonance densitometry

Becker, B.*; 原田 秀郎; Kauwenberghs, K.*; 北谷 文人; 小泉 光生; Kopecky, S.*; Moens, A.*; Schillebeeckx, P.*; Sibbens, G.*; 土屋 晴文

Proceedings of 35th ESARDA Annual Meeting (Internet), 7 Pages, 2013/05

Neutron Resonance Densitometry (NRD) represents a possible option to determine the heavy metal content in melted nuclear fuel. It is a non-destructive method and is applicable for highly radioactive material. The accuracy of NRD depends among other factors on sample characteristics. Inhomogeneities such as density variations in powder samples can introduce a significant bias in the determination of the composition. In this contribution, the impact of the particle size distribution of such powder samples on results obtained with NRD is investigated. Various analytical models, describing the neutron transport through powder, are compared. Stochastic numerical simulations are used to select a specific model and to estimate the introduced model uncertainty. The results from these simulations will be verified by dedicated measurements at the TOF-facility GELINA of the EC-JRC-IRMM.

論文

Development of neutron resonance densitometry at the GELINA TOF facility

Schillebeeckx, P.*; Abousahl, S.*; Becker, B.*; Borella, A.*; Emiliani, F.*; 原田 秀郎; Kauwenberghs, K.*; 北谷 文人; 小泉 光生; Kopecky, S.*; et al.

Proceedings of 35th ESARDA Annual Meeting (Internet), 11 Pages, 2013/05

Neutron Resonance Capture Analysis (NRCA) and Neutron Resonance Transmission Analysis (NRTA) have been applied to determine the elemental composition of archaeological objects and to characterize nuclear reference materials. A combination of NRTA and NRCA, referred to as Neutron Resonance Densitometry (NRD), is being studied as a non-destructive method to characterize particle-like debris of melted fuel that is formed in severe nuclear accidents such as the one which occurred at the Fukushima Daiichi Nuclear Power Plants. This study is part of a collaboration between JAEA and EC-JRC-IRMM. In this contribution the basic principles of NRTA and NRCA are explained based on the experience in the use of these methods at the time-of-flight facility GELINA of the EC-JRC-IRMM. Specific problems related to the analysis of samples resulting from melted fuel are discussed. The programme to study and solve these problems is described and results of a first measurement campaign at GELINA are given.

口頭

NDA R&D activities at JAEA

呉田 昌俊; 小泉 光生; 原田 秀郎; 瀬谷 道夫; 直井 洋介

no journal, , 

原子力機構は、新たにEC-JRCとの国際共同研究による「(仮)パルス中性子源を用いたDDA法、DG法, NRCA/PGA法, NRTA法から構成されるアクティブ中性子非破壊測定技術開発」に着手する。本研究課題の最終目標は、再処理サイクル過程で存在している使用済燃料など高線量核燃料や、核不拡散関連装置への適用を目指した核物質測定技術を確立することである。本研究課題において、アクティブ中性子法による核物質測定技術の研究開発および個々の技術の組み合わせに関して研究を行う。

口頭

Challenge towards quantification of SNM from Fukushima Daiichi by NRD

原田 秀郎; 小泉 光生; 土屋 晴文; 北谷 文人; 瀬谷 道夫; Becker, B.*; Heyse, J.*; Kopecky, S.*; Paradela, C.*; Schillebeeckx, P.*

no journal, , 

原子力機構は、原子力発電所の事故で発生するような燃料デブリ中の核燃料を非破壊で計測するため、中性子共鳴濃度分析法の概念を提唱し、EC-JRC-IRMMとの国際共同研究により、IRMMのパルス中性子発生施設を用いて技術開発を進め、その有効性を示す試験データを取得すると共に、並行して分析手法の開発を進めてきた。本講演では、中性子共鳴濃度分析法の概念を概説するとともに、本共同研究により得られた主要な研究成果である、ウラン試料を用いた分析結果、構造材料の同定結果、非均一の粒子状サンプルを用いた分析結果、さらに任意形状のサンプルを分析可能とする解析手法等について解説する。

口頭

Development of active neutron NDA techniques

呉田 昌俊

no journal, , 

原子力機構は、EC-JRCとの国際共同研究による「アクティブ中性子非破壊測定技術開発」に着手した。本研究課題の最終目標は、MA核変換用MA-Pu燃料など高線量核燃料や、核セキュリティ関連装置への適用を目指した核物質測定技術を確立することである。本研究課題では、アクティブ中性子法であるDDA法, NRTA法, PGA/NRCA法, DGS法による核物質測定技術の研究開発を行う。

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