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Measurements of the $$^{243}$$Am neutron capture and total cross sections with ANNRI at J-PARC

木村 敦; 中村 詔司; 寺田 和司*; 中尾 太郎*; 水山 一仁*; 岩本 信之; 岩本 修; 原田 秀郎; 片渕 竜也*; 井頭 政之*; et al.

Journal of Nuclear Science and Technology, 56(6), p.479 - 492, 2019/06

Neutron total and capture cross sections of $$^{243}$$Am have been measured in Accurate Neutron Nucleus Reaction measurement Instrument at Materials and Life Science Experimental Facility of Japan Proton Accelerator Research Complex with a neutron TOF method. The neutron capture cross section in the energy region from 10 meV to 100 eV was determined using an array of Ge detectors. Three samples with different activities were used for measurements of the capture cross section. The neutron total cross section in the energy region from 4 meV to 100 eV was measured using Li-glass detectors. Derived cross-section value at neutron energy of 0.0253 eV is 87.7$$pm$$5.4 b for the capture cross section and 101$$pm$$11 b for the total cross section.


Measurements of neutron total and capture cross sections of $$^{241}$$Am with ANNRI at J-PARC

寺田 和司*; 木村 敦; 中尾 太郎*; 中村 詔司; 水山 一仁*; 岩本 信之; 岩本 修; 原田 秀郎; 片渕 竜也*; 井頭 政之*; et al.

Journal of Nuclear Science and Technology, 55(10), p.1198 - 1211, 2018/10

 被引用回数:1 パーセンタイル:38.14(Nuclear Science & Technology)

Neutron total and capture cross sections of $$^{241}$$Am have been measured with a new data acquisition system and a new neutron transmission measurement system installed in Accurate Neutron Nucleus Reaction measurement Instrument (ANNRI) at Materials and Life Science Experimental Facility (MLF) of Japan Proton Accelerator Research Complex (J-PARC). The neutron total cross sections of $$^{241}$$Am were determined by using a neutron time-of-flight method in the neutron energy region from 4 meV to 2 eV. The thermal total cross section of $$^{241}$$Am was derived with an uncertainty of 2.9%. A pulse-height weighting technique was applied to determine neutron capture yields of $$^{241}$$Am. The neutron capture cross sections were determined by the time-of-flight method in the neutron energy region from the thermal to 100 eV, and the thermal capture cross section was obtained with an uncertainty of 4.1%. The evaluation data of JENDL-4.0 and JEFF-3.2 were compared with the present results.


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.


Measurement of MA reaction rates using spallation neutron source

大泉 昭人; 福島 昌宏; 辻本 和文; 山中 正朗*; 佐野 忠史*; Pyeon, C. H.*

KURRI Progress Report 2017, P. 50, 2018/08



Neutron irradiation effect of high-density MoO$$_{3}$$ pellets for Mo-99 production

藤田 善貴; 西方 香緒里; 滑川 要二*; 木村 明博; 柴田 晃; 佐谷戸 夏紀; 土谷 邦彦; 佐野 忠史*; 藤原 靖幸*; Zhang, J.*

KURRI Progress Report 2017, P. 126, 2018/08



Systematic effects on cross section data derived from reaction rates in reactor spectra and a re-analysis of $$^{241}$$Am reactor activation measurements

$v{Z}$erovnik, G.*; Schillebeeckx, P.*; Becker, B.*; Fiorito, L.*; 原田 秀郎; Kopecky, S.*; Radulovic, V.*; 佐野 忠史*

Nuclear Instruments and Methods in Physics Research A, 877, p.300 - 313, 2018/01

 被引用回数:1 パーセンタイル:38.14(Instruments & Instrumentation)



Research and development for accuracy improvement of neutron nuclear data on minor actinides

原田 秀郎; 岩本 修; 岩本 信之; 木村 敦; 寺田 和司; 中尾 太郎; 中村 詔司; 水山 一仁; 井頭 政之*; 片渕 竜也*; et al.

EPJ Web of Conferences (Internet), 146, p.11001_1 - 11001_6, 2017/09

 被引用回数:1 パーセンタイル:14.04

A nuclear data project entitled Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC) is being performed in Japan. The objective of the project is to improve accuracy of neutron nuclear data for minor actinides and some fission products, which is required for developing innovative nuclear system transmuting these nuclei. Following research items have been conducted to achieve the objective: (1) Measurements of thermal neutron capture cross-sections by activation methods, (2) High-precision quantifications of shielded sample amounts used for TOF measurement, (3) Resonance parameter determinations at J-PARC/ANNRI and KURRI/LINAC, (4) Extension of capture cross sections to high energy neutrons at J-PARC/ANNRI, (5) High quality evaluation based on iterative communication with experimenters. The achievement of the project is presented.


Improving nuclear data accuracy of $$^{241}$$ Am and $$^{237}$$ Np capture cross sections

$v{Z}$erovnik, G.*; Schillebeeckx, P.*; Cano-Ott, D.*; Jandel, M.*; 堀 順一*; 木村 敦; Rossbach, M.*; Letourneau, A.*; Noguere, G.*; Leconte, P.*; et al.

EPJ Web of Conferences (Internet), 146, p.11035_1 - 11035_4, 2017/09

 被引用回数:2 パーセンタイル:4.05

There is a serious gap between required accuracy and current accuracy on nuclear data for developing innovative nuclear reactor systems. To bridge this gap, an international joint activity entitled Improving Nuclear Data Accuracy of $$^{241}$$Am and $$^{237}$$Np capture cross sections (INDA) has being performed under WPEC. In this joint study, the forefront knowledge of energy dependent cross section measurements, spectrum averaged experiments, relevant nuclear structure data, and evaluations are intended to be integrated on the capture cross sections of $$^{241}$$Am and $$^{237}$$Np. From the joint study, it was shown that integration of knowledge from the independent specialities enables us not only to crosscheck between data obtained by different techniques but also to improve the measurement accuracy of each other.


Analysis of energy resolution in the KURRI-LINAC pulsed neutron facility

佐野 忠史*; 堀 順一*; 高橋 佳之*; 八島 浩*; Lee, J.*; 原田 秀郎

EPJ Web of Conferences (Internet), 146, p.03031_1 - 03031_3, 2017/09

 被引用回数:1 パーセンタイル:14.04

We carried out Monte Carlo calculation to provide energy resolution of pulsed neutron beam for TOF measurements in the KURRI-LINAC pulsed neutron facility. The calculations were performed for moderated neutron flux at the energy range from 0.01 eV to 20 MeV. As the result, we obtained the energy resolutions ($$Delta$$E/E) in the epi-thermal region. For example, the energy resolutions were 1.0% in the neutron energy of 1.0 eV, 1.1% in 100.0 eV and 1.7% in 1.0 keV.


High precision analysis of isotopic composition for samples used for nuclear cross-section measurements

芝原 雄司*; 堀 順一*; 高宮 幸一*; 藤井 俊行*; 福谷 哲*; 佐野 忠史*; 原田 秀郎

EPJ Web of Conferences (Internet), 146, p.03028_1 - 03028_4, 2017/09


For the accuracy improvement of nuclear data of minor actinides and long-lived fission products in AIMAC project, high quality data of the isotopic composition of samples are indispensable. The objective of this research is to obtain the isotopic composition data of samples contributing to the analysis of nuclear cross-section measurement data by mass spectrometry etc. In this study, we analyzed the isotopic composition of two Am samples ($$^{241}$$ Am sample and $$^{243}$$ Am sample) mainly by the thermal ionization mass spectrometry (TIMS). In addition to the TIMS, Am samples were also analyzed by $$alpha$$-spectrometry. In the analysis by both methods, the impurities such as $$^{239}$$Pu, $$^{240}$$Pu, $$^{242}$$Cm and$$^{244}$$Cm were also observed. The results of these analyses are presented together with the developed high precision analytical method.


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 (Internet), 146, p.09032_1 - 09032_3, 2017/09


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.


Neutron irradiation effect of high-density MoO$$_{3}$$ pellets for Mo-99 production, 3

石田 卓也; 鈴木 善貴; 西方 香緒里; 米川 実; 加藤 佳明; 柴田 晃; 木村 明博; 松井 義典; 土谷 邦彦; 佐野 忠史*; et al.

KURRI Progress Report 2015, P. 64, 2016/08



Activation measurements of neputunium-237 at KURRI-Linac

中村 詔司; 寺田 和司; 芝原 雄司*; 上原 章寛*; 藤井 俊行*; 佐野 忠史*; 高橋 佳之*; 堀 順一*

KURRI Progress Report 2015, P. 67, 2016/08



Measurements of americium isotopes by activation method at KURRI-Linac

中村 詔司; 寺田 和司; 高橋 佳之*; 佐野 忠史*; 堀 順一*

KURRI Progress Report 2015, P. 69, 2016/08



Activation experiments for verification of neutron capture cross section of $$^{237}$$Np using variable neutron field at KURRI-LINAC

高橋 佳之*; 堀 順一*; 佐野 忠史*; 八木 貴宏*; 八島 浩*; Pyeon, C. H.*; 中村 詔司; 原田 秀郎

Proceedings of International Conference on the Physics of Reactors; Unifying Theory and Experiments in the 21st Century (PHYSOR 2016) (USB Flash Drive), p.645 - 652, 2016/05

放射性毒性の低減のために、マイナーアクチニド(MA)及び長寿命核分裂生成核種(LLFP)の革新的原子炉を用いた核変換の実用化研究が精力的に進められてきている。革新的な原子炉システムを設計するためには、正確な核データが必要である。そこで、精度の高い核データの整備のために、マイナーアクチニドの中性子核データの高精度化研究を行うAIMACプロジェクトが始められている。本プロジェクトの一環として、京都大学原子炉実験所の電子線形加速器(KURRI-LINAC)や臨界集合体(KUCA)における可変中性子場を用いて、マイナーアクチニドの核データ(積分データ)を測定する。$$^{237}$$Np, $$^{241}$$Am,そして$$^{243}$$Am核種について、本研究で得られる積分データを、別途、TOF測定で得られた微分断面積データと比較検討を行うことで、核データの検証を行う。本論文では、$$^{237}$$Npの中性子捕獲反応の反応率の測定結果を報告する。


チェレンコフ光観測の原子炉計測への適用,2; チェレンコフ光評価システムの設計・試作

山本 圭一; 武内 伴照; 林 隆康*; 小菅 史明*; 佐野 忠史*; 土谷 邦彦

JAEA-Testing 2015-001, 25 Pages, 2015/11





石田 卓也; 椎名 孝行*; 太田 朗生*; 木村 明博; 西方 香緒里; 柴田 晃; 棚瀬 正和*; 小林 正明*; 佐野 忠史*; 藤原 靖幸*; et al.

JAEA-Technology 2015-030, 42 Pages, 2015/11




Systematic effects on cross-section data derived from reaction rates at a cold neutron beam

$v{Z}$erovnik, G.*; Becker, B.*; Belgya, T.*; Genreith, C.*; 原田 秀郎; Kopecky, S.*; Radulovi$'c$, V.*; 佐野 忠史*; Schillebeeckx, P.*; Trkov, A.*

Nuclear Instruments and Methods in Physics Research A, 799, p.29 - 36, 2015/11

 被引用回数:4 パーセンタイル:43.49(Instruments & Instrumentation)



Neutron irradiation effect of high-density MoO$$_{3}$$ pellets for Mo-99 production, 2

西方 香緒里; 石田 卓也; 米川 実; 加藤 佳明; 黒澤 誠; 木村 明博; 松井 義典; 土谷 邦彦; 佐野 忠史*; 藤原 靖幸*; et al.

KURRI Progress Report 2014, P. 109, 2015/07



Development of in-reactor observation system using Cherenkov light(VI)

武内 伴照; 山本 圭一; 大塚 紀彰; 柴田 裕司; 柴田 晃; 竹本 紀之; 土谷 邦彦; 佐野 忠史*; 宇根崎 博信*; 藤原 靖幸*; et al.

KURRI Progress Report 2014, P. 108, 2015/07


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