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Gd and 
Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC
MLFANNRI木村 敦; 中村 詔司; 遠藤 駿典; Rovira Leveroni, G.; 岩本 修; 岩本 信之; 原田 秀郎; 片渕 竜也*; 寺田 和司*; 堀 順一*; et al.
Journal of Nuclear Science and Technology, 60(6), p.678 - 696, 2023/06
被引用回数：2 パーセンタイル：72.55(Nuclear Science & Technology)Neutron total and capture cross-section measurements of Gd and Gd were performed in the ANNRI at the MLF of the J-PARC. The neutron total cross sections were determined in the energy region from 5 to 100 meV. At the thermal neutron energy, the total cross sections were obtained to be 59.4
1.7 and 251.94.6 kilobarn for Gd and Gd, respectively. The neutron capture cross sections were determined in the energy region from 3.5 to 100 meV with an innovative method by taking the ratio of the detected capture event rate between thin and thick samples. At the thermal energy, the capture cross sections were obtained as 59.02.5 and 247.43.9 kilobarn for Gd and Gd, respectively. The present total and capture cross sections agree well within the standard deviations. The results for Gd were found to be consistent with the values in JENDL-4.0 and the experimental data given by Mastromarco et al. and Leinweber et al. within one standard deviation. Moreover, the present results for Gd agreed with the evaluated data in JENDL-4.0 and the experimental data by M
ller et al. within one standard deviation and agreed with the data by Mastromarco et al. within 1.4 standard deviations. However, they disagree (11% larger) with the experimental result by Leinweber et al.
Am neutron capture cross section in the keV region using Si and Fe-filtered neutron beamsRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*
Journal of Nuclear Science and Technology, 60(5), p.489 - 499, 2023/05
被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)The neutron capture cross-section of Am was measured in the keV neutron range using the recently implemented neutron filtering system of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). Filter arrays consisting of 20 cm of 
Fe and Si were employed in separate measurements to provide filtered neutron beams with averaged neutron energies of 23.5 (Fe), 51.5 and 127.7 (Si) keV. The present Am results were obtained relative to the 
Au neutron capture yield by applying the total energy detection principle together with the pulse-height weighting technique. The Am neutron capture cross section was determined as 2.72 0.29 b at 23.5 keV, 2.14 0.26 b at 51.5 keV and 1.32 0.10 b at 127.7 keV with total uncertainties in the range of 8 to 12
, much lower in comparison to the latest time-of-flight experimental data available.
遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.
EPJ Web of Conferences, 281, p.00012_1 - 00012_5, 2023/03
In resonance analysis, experimental uncertainties affect the accuracy of resonance parameters. A resonance analysis code REFIT can consider the statistical uncertainty of the experimental data in evaluation of the resonance parameter uncertainty. On the other hand, since the systematic uncertainties of the sample thickness and normalization, which is proportional to the cross-section, are not independent at each measurement point, they must be treated differently from the statistical uncertainty. However, their treatment has not been discussed in detail so far. In this study, we evaluated the effect of the systematic uncertainties of experimental data on deduced resonance parameters by varying sample-thickness values used for the REFIT code. Covariance of resonance parameters ascribed to systematic uncertainties were evaluated from the neutron transmission data of natural zinc measured at the J-PARC MLF ANNRI. We will introduce this evaluation method and discuss the feature of obtained correlations.
片渕 竜也*; 岩本 修; 堀 順一*; 木村 敦; 岩本 信之; 中村 詔司; Rovira Leveroni, G.; 遠藤 駿典; 芝原 雄司*; 寺田 和司*; et al.
EPJ Web of Conferences, 281, p.00014_1 - 00014_4, 2023/03
Long-lived minor actinides (MA) in nuclear waste from nuclear power plants are a long-standing issue to continue nuclear energy production. To solve the issue, researchers have suggested nuclear transmutation, in which long-lived radionuclides are transmuted into stable or shorter-life nuclides via neutron-induced nuclear reactions. Development of nuclear transmutation systems as an accelerator-driven system requires accurate neutron nuclear reaction data. The present research project entitled "Study on accuracy improvement of fast-neutron capture reaction data of long-lived MAs for development of nuclear transmutation systems" have been conducted as a joint collaboration, including Tokyo Tech, Japan Atomic Energy Agency and Kyoto University. This project focuses on the neutron capture reaction of MAs, especially 
Np, Am and 
Am, in the fast neutron energy region. The final goal of this project is to improve the accuracies of the neutron capture cross sections of Np, Am and Am employing a high-intensity neutron beam from a spallation source of the Japan Proton Accelerator Research Complex (J-PARC) that reduces uncertainties of measurement. To achieve the goal, a neutron beam filter system in J-PARC, sample characteristic assay, and theoretical reaction model study were developed. In this contribution, the overview and results of the project will be presented.
Am neutron capture cross section measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*
Journal of Nuclear Science and Technology, 19 Pages, 2023/00
The neutron capture cross-section of Am was measured from 10 meV to about 1 MeV using the NaI(Tl) spectrometer of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). The total energy detection principle was applied in conjunction with the pulse-height weighting technique to derive the neutron capture yield. The present cross-section results were normalized using a Au sample measurement by applying the saturated resonance method. The thermal cross section was measured to be 708 22 b, in agreement within uncertainties to the present evaluation in JENDL-5 of 709 b. Moreover, the results of a shape resonance analysis of the resolved resonance region are also provided in the present dissertation.
中野 秀仁*; 片渕 竜也*; Rovira Leveroni, G.; 児玉 有*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典
Journal of Nuclear Science and Technology, 59(12), p.1499 - 1506, 2022/12
被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)A neutron monitoring detection system was developed for neutron capture cross section measurement using a spallation neutron source. A combination of a plastic scintillator and a thin 
LiF foil was adopted for the detector. The detector system was tested to study the feasibility of the system. Neutron irradiation experiments were conducted with the Accurate Neutron-Nucleus Reaction Measurement Instrument in the Materials and Life Science facility of the Japan Proton Accelerator Research Complex. A neutron time-of-flight spectrum was successfully measured without significant count loss or detector paralysis. The statistical uncertainty reached 0.7% at neutron energies around 6 meV.
Am neutron capture cross section measurement and resonance analysisRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*
JAEA-Conf 2022-001, p.91 - 96, 2022/11
Neutron capture cross section measurements were performed in the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Materials and Life Science Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC). The time-of-flight (TOF) methodology was employed in a non-filter condition experiment to determine the neutron capture cross section from thermal to about 100 eV. Moreover, experiments were performed using the neutron filtering system to determine the neutron capture cross section at the energy of 23.5 keV using Fe as filter material. In this study, the preliminary results of the Am neutron capture cross section from 10 meV to about 100 eV determined in TOF experiments and at 23.5 keV from Fe filter experiments are presented. In the TOF experiments, the Am neutron capture cross section was normalized by means of the saturated resonance method using a Au sample with a mass of 1.5 g. In addition, for the Fe filter experiments, the capture cross section of Am at the energy of 23.5 keV was determined relative to the Au yield obtained from a measurement using the same Au sample. Moreover, early-stage results of a resonance analysis of the Am capture resonances are also presented.
Au with a Cr-filtered neutron beam at the ANNRI beamline of MLF/J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*; et al.
Journal of Nuclear Science and Technology, 59(5), p.647 - 655, 2022/05
被引用回数：1 パーセンタイル：21.98(Nuclear Science & Technology)Cr-filtered keV-neutron experiments were performed in the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC) to measure the neutron capture cross-section of Au. The energy range of the neutron filtering system at ANNRI was extended through the use of 15 cm of Cr as filter material to tailor quasi-monochromatic neutron peaks with averaged neutron energies of 133.4 and 45.0 keV. The performance of the Cr filter assembly was evaluated by means of experimental capture and transmission analyses, together with the use of Monte-Carlo simulations. The present Au neutron capture cross-section results provide agreement within uncertainties with the JENDL-4.0 standard evaluated library and the IAEA standard data library further demonstrating the capabilities of the neutron filtering system at ANNRI.
Rovira Leveroni, G.; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之; 遠藤 駿典; 片渕 竜也*; 寺田 和司*; 児玉 有*; 中野 秀仁*; et al.
JAEA-Conf 2021-001, p.156 - 161, 2022/03
A neutron filtering system has been designed in order to bypass the double-timed structure of the beam. Filter materials were introduced into the rotary collimator of the ANNRI beamline in order to produce quasi-monoenergetic neutron filtered beams. Filter assemblies consisting of Fe with a thickness of 20 cm, and Si with thicknesses of 20 cm and 30 cm of Si were used separately to produce filtered neutron peaks with energies of 24 keV (Fe) and of 54 and 144 (Si). In this study, the characteristics and performance of the neutron filtering system at ANNRI using Fe and Si determined from both measurements and simulations are presented. The incident neutron flux was tested and analyzed by means of transmission and capture experiments. Moreover, simulations using the PHITS code were performed in order to determine the energy distribution of the integrated filtered peaks and assess the reliability of experimental results. Finally, preliminary results of the capture cross section of Au at the filtered energies of 24, 54 and 144 keV are also presented using the NaI(Tl) spectrometer alongside the neutron filtering system.
中野 秀仁*; 片渕 竜也*; Rovira Leveroni, G.*; 児玉 有*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典
JAEA-Conf 2021-001, p.166 - 170, 2022/03
In neutron capture cross section measurement, monitoring the number of the incident neutrons is necessary. However, in measurement with J-PARC/ANNRI, direct neutron monitoring system has not been employed. Conventional neutron detectors cannot be used as a beam monitor at ANNRI because of two reasons, high counting rate environment and gamma-flash. In general, a semiconductor detector or an inorganic scintillator, which is adopted for a neutron detector, has relatively longer response time and is unsuitable for beam monitoring at ANNRI. Therefore, a combination of a thin plastic scintillator and a LiF foil was selected as a detection system, whose fast response enabled detecting neutrons at a high counting rate. Low gamma ray sensitivity of a thin plastic scintillator allows measuring fast TOF region without count loss or detector paralysis. The geometry of the LiF foil, the plastic scintillator, and photomultiplier tube (PMT) was designed. The optimal thickness of the LiF foil was determined with simulation codes, SRIM and PHITS. The detector system was tested under the high neutron irradiation condition at J-PARC /ANNRI. A neutron TOF spectrum was successfully measured without significant count loss or detector paralysis. A neutron energy spectrum was driven from difference of TOF spectrum with and without LiF. The neutron spectrum was compared with a past neutron spectrum and good agreement was obtained. Statistic error was 0.68 at 6.0 meV even though measurement times in this study were short.
児玉 有*; 片渕 竜也*; Rovira Leveroni, G.; 中野 秀仁*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典
JAEA-Conf 2021-001, p.162 - 165, 2022/03
Precise nuclear data for neutron-induced reactions are necessary for the design of nuclear transmutation systems. Nevertheless, current uncertainties of nuclear data for minor actinide (MA) does not achieve requirements for the design of transmutation facilities. The determination of an incident neutron flux for measurements of neutron capture cross section is one of the main causes that affect the final uncertainty of the cross section results. In the present work, we suggest a new method to reduce systematic uncertainties of capture cross section measurements. The method employs change of the self-shielding effect with sample rotation angle. In capture cross section measurements in ANNRI, a boron sample is placed to determine the incident neutron spectrum by counting 478 keV 
-ray from the 
reaction. In this method, the boron sample is tilted with respect to the neutron beam direction, thereby changing the effective area. This results in change of the shapes of time-of-flight (TOF) spectrum of 478 keV -ray from the reaction with the tilted angle. Comparing the difference of the TOF spectra at different angles and assuming the 1/v energy dependence of cross section of the reaction, the area density of the boron sample can be determined without using the sample mass and area. Theoretical and experimental studies on the new method are ongoing. Calculation using Monte Carlo simulation code PHITS were carried out to study the feasibility of the present method. Test experiments using a sample rotation system at ANNRI were also performed.
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：2 パーセンタイル：21.98(Nuclear Science & Technology)In order to improve the accuracy of the cross-section and the resonance parameters of 
Nb, neutron capture and total cross-sections were measured using the J-PARC MLF ANNRI. The thermal-neutron capture cross-section was deduced as 0.970.12 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.
NpRovira Leveroni, G.; 片渕 竜也*; 登坂 健一*; 松浦 翔太*; 児玉 有*; 中野 秀仁*; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之
Journal of Nuclear Science and Technology, 59(1), p.110 - 122, 2022/01
被引用回数：1 パーセンタイル：21.98(Nuclear Science & Technology)Neutron capture cross-section measurements for Np have been conducted with the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Materials and Life Science Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC) using neutrons with energy ranging from thermal energy to 1 MeV. A Time of Flight (TOF) method using a NaI(Tl) detector was employed for these measurements and the data were analyzed based on the pulse-height weighting technique in order to derive the neutron capture cross-section. The absolute capture cross-section was determined using the whole shape of the first resonance from JENDL-4.0 together with the total neutron flux derived from a Au sample measurement in which the first resonance was completely saturated. Both normalization techniques present agreement within 2%. The present results are also compared evaluated data libraries. There is a discrepancy of 10-25% discrepancy from 0.5 to 20 keV with JENDL-4.0. Nonetheless, above this energy, the JENDL-4.0 seems to reproduce the present data better as the results agree within uncertainties up to 500 keV. The cross-section results contain errors below 4% from 0.5 to 30 keV. However, the total uncertainty increases to over 8% over that energy. Along with the cross section measurement, theoretical calculations were performed to reproduce the present results.
Am around 23.5 keV児玉 有*; 片渕 竜也*; Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 信之; 岩本 修; 堀 順一*; 芝原 雄司*; et al.
Journal of Nuclear Science and Technology, 58(11), p.1159 - 1164, 2021/11
被引用回数：3 パーセンタイル：56.29(Nuclear Science & Technology)The neutron capture cross section of Am was measured with a pulsed neutron beam from a spallation neutron source of the Japan Proton Accelerator Research Complex. A Fe neutron beam filter was used to make the incident neutron beam mono-energetic around 23.5 keV. The neutron capture -rays were detected with a NaI(Tl) detector. The pulse height weighting technique was employed to derive the neutron capture cross section from the pulse height spectrum. The cross section was determined relative to the capture cross section of Au of JENDL-4.0. The neutron capture cross section of Am was determined with a smaller uncertainty than previous measurements. The previous measurements and the JENDL-4.0 cross sections were found to be lower than the present result.
Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 寺田 和司*; 児玉 有*; 中野 秀仁*; et al.
Nuclear Instruments and Methods in Physics Research A, 1003, p.165318_1 - 165318_10, 2021/07
被引用回数：3 パーセンタイル：56.39(Instruments & Instrumentation)A neutron filtering system has been introduced in the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Material and Life Science (MLF) building of the Japan Proton Accelerator Research Complex (J-PARC) in order to produce quasi-monoenergetic neutron beams. The filtered neutron spectrum by the filter assemblies was analyzed by means of capture and transmission measurements and also by Monte Carlo simulations using PHITS. The characteristics of the filtered neutron beam are discussed alongside its viability in future applications for neutron cross-section measurements in the fast neutron region.
Y片渕 竜也*; 藤 暢輔; 水本 元治*; 齋藤 辰宏*; 寺田 和司*; 木村 敦; 中村 詔司; Huang, M.*; Rovira Leveroni, G.; 井頭 政之*
European Physical Journal A, 57(1), p.4_1 - 4_4, 2021/01
被引用回数：1 パーセンタイル：24.48(Physics, Nuclear)A new neutron resonance of Y was found in time-of-flight (TOF) neutron capture experiments using a pulsed neutron beam from a spallation neutron source of the Japan Proton Accelerator Research Complex. The observed resonance energy was 19.7 eV that is much lower than the lowest energy (2.60 keV) of the previous reported resonances. In addition to the TOF measurement, nuclide identification of the resonance was made by prompt -ray analysis. Neutron capture -rays from Y were clearly observed only on the resonance. Resonance analysis was applied to the experimental results and the resonance parameters of the new resonance are given.
Rovira Leveroni, G.
核データニュース(インターネット), (126), p.34 - 42, 2020/06
The contents and results of my doctoral thesis conducted at Tokyo Tech for the last 3 years are presented in the journal. The doctoral dissertation consisted on the measurement of the neutron capture cross-section of Np. The article contents include the background of the research, experimental setup, resonance analysis, results and conclusions. At the end of the article I also explain about my life experience in Japan as a student from another country.
岩本 信之; 岩本 修; 中村 詔司; 木村 敦; 片渕 竜也*; Rovira Leveroni, G.*
no journal, ,
高速中性子エネルギー領域における中性子捕獲断面積に対して、統計モデルによる計算精度を高めるには、ガンマ線強度関数の情報が重要である。これは、ガンマ線強度関数が励起状態間のガンマ線による遷移強度を与えるためであり、放出ガンマ線のスペクトルに直接関係するからである。ガンマ線強度関数に関する情報はいくつかの実験手法で得られているが、J-PARC・物質生命科学実験施設の中性子核反応測定装置(ANNRI)に設置されたガンマ線検出器で得られる波高スペクトル情報もガンマ線強度関数を評価するのに有効である。放射線輸送コードPHITSを使って、ANNRIのNaI(Tl)検出器に対するガンマ線応答関数を導出し、これを核反応計算コードCCONEでガンマ線強度関数から計算した捕獲ガンマ線スペクトルにフォールディングすることで波高スペクトルを求めた。得られた波高スペクトルとNaI(Tl)検出器で測定された結果を比較することで、ガンマ線強度関数を評価した。発表では、このガンマ線強度関数を基に計算したガンマ線スペクトルや中性子捕獲断面積などの結果を報告する。
Taの中性子全断面積および捕獲断面積の測定遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.
no journal, ,
タンタル(Ta)の中性子断面積の高精度化を目指し、J-PARC・MLF・ANNRIにてリチウムガラス検出 器およびゲルマニウム検出器を用い、飛行時間法にてTaの中性子全断面積および捕獲断面積の測定を行った。得られたスペクトルデータから0.01eV
50eVの領域の中性子断面積を導出した。
岩本 信之; 岩本 修; Rovira Leveroni, G.; 中村 詔司; 木村 敦; 片渕 竜也*
no journal, ,
J-PARC・MLF・ANNRIのNaI(Tl)検出器では高速中性子エネルギー領域までの捕獲断面積と波高スペクトルの測定ができる。このうち波高スペクトルは捕獲断面積計算に重要なガンマ線強度関数と直接的な関係がある。本研究では、放射線輸送コードPHITSによりNaI(Tl)検出器でのガンマ線応答をシミュレーションすることで、各ガンマ線エネルギーに対する応答関数を計算し、核反応計算コードCCONEで計算したガンマ線スペクトルにこの応答関数を適用することで波高スペクトルを導出した。そして、計算で得た波高スペクトルを測定された波高スペクトルと比較することで、ガンマ線強度関数の評価を可能にした。MA核種(Npなど)に対し、本手法を適用して得られたガンマ線強度関数を基に、本研究及び既存の捕獲断面積測定データを利用することで断面積評価及び共分散評価を行ったので、その結果を報告する。
