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論文

Single crystal growths and magnetic properties of hexagonal polar semimetals $$R$$AuGe ($$R$$ = Y, Gd-Tm, and Lu)

車地 崇*; 厳 正輝*; 鬼頭 俊介*; 池内 和彦*; 中村 充孝; 池田 暁彦*; 有馬 孝尚*

Journal of Alloys and Compounds, 947, p.169475_1 - 169475_8, 2023/06

https://doi.org/10.1016/j.jallcom.2023.169475
 被引用回数：0

We study structural and magnetic properties of rare-earth based semimetals ${it R}$AuGe (${it R}$ = Y, Gd-Tm, and Lu) using flux-grown single crystals. We evaluate the crystal electric field parameters based on the Stevens operators to reasonably reproduce the temperature dependence of magnetic susceptibilities and specific heat for RAuGe (${it R}$ = TbTm). The estimated energy scale of the Ising gap ($$sim$$ 11 meV) in TmAuGe is consistent with an excitation observed in an inelastic neutron scattering experiment. These findings suggest an opportunity for interplay between conduction electrons and nontrivial spin structures in the family of magnetic polar semimetals ${it R}$AuGe.

論文

Covariance of resonance parameters ascribed to systematic uncertainties in experiments

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

https://doi.org/10.1051/epjconf/202328100012

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.

論文

Water contents in aggregates and cement pastes determined by gravimetric analysis and prompt $$gamma$$-ray analysis

木下 哲一*; 能任 琢真*; 中島 均*; 小迫 和明*; 加藤 雄大*; 黒岩 洋一*; 倉部 美彩子*; 佐々木 勇気*; 鳥居 和敬*; 前田 亮; et al.

Journal of Radioanalytical and Nuclear Chemistry, 332(2), p.479 - 486, 2023/02

https://doi.org/10.1007/s10967-023-08776-w

There are some different chemical and physical forms of water molecules in concretes. Especially, bound water is difficult to determine. In the present work, we determined free + adsorbed water and bound water contained in aggregates and cement pastes, which are component of concretes, by means of conventional gravimetric analysis and prompt $$gamma$$-ray analysis (PGA), respectively, in order to evaluate a total water content in concretes. In the PGA, background reduction was attempted by using the time-of-flight (TOF) signal. In addition, the degree of contribution to analytical values by scattered neutrons by samples was evaluated because water would adsorb on the surface of instruments inside the irradiation chamber for the PGA. Contents of the free + adsorbed water and bound water in some geochemical references determined in the present work were compared with the nominal values to confirm the precision. Each water content in aggregates collected from different quarries and cement pastes with different water-to-cement ratios were analyzed. A total water content in young concrete was evaluated on the basis of the analytical values.

論文

Neutron capture cross-section measurement by mass spectrometry for Pb-204 irradiated in JRR-3

中村 詔司; 芝原 雄司*; 木村 敦; 遠藤 駿典; 静間 俊行*

Journal of Nuclear Science and Technology, 10 Pages, 2023/00

https://doi.org/10.1080/00223131.2023.2172088
 被引用回数：0 パーセンタイル：0.05(Nuclear Science & Technology)

近年、鉛冷却高速炉や加速器駆動システムの研究が進められており、Pb同位体の中性子捕獲断面積の高精度化が求められている。$$^{204}$$Pbは、天然存在比は小さいが中性子捕獲反応により長寿命放射性核種$$^{205}$$Pb(1730万年)を作るため、その重要性は高いと考えられる。しかし、原子炉を用いた通常の放射化法では、生成する$$^{205}$$Pbからの放射線が弱いため測定するのが難しい。そこで、マススペクトロメトリーを適用した断面積測定を行った。本発表ではマススペクトロメトリーを適用した$$^{204}$$Pbの中性子捕獲断面積測定について実験の詳細と得られた結果を報告する。

論文

Measurements of capture cross-section of $$^{93}$$Nb by activation method and half-life of $$^{94}$$Nb by mass analysis

中村 詔司; 芝原 雄司*; 遠藤 駿典; 木村 敦

Journal of Nuclear Science and Technology, 11 Pages, 2023/00

https://doi.org/10.1080/00223131.2023.2198526

廃止措置の対象核種の中から$$^{93}$$Nbについて、熱中性子捕獲断面積($$sigma$$$$_{0}$$)および共鳴積分(I$$_{0}$$)を放射化法により測定した。また、$$^{94}$$Nbの半減期を質量分析により測定した。ニオブ93試料は、京都大学複合原子力科学研究所の研究炉に整備されている水圧輸送艦を用いて照射した。金-アルミ合金線、およびコバルト-アルミ合金線を用いて、照射位置における中性子束成分を測定した。厚さ25$$mu$$mのガドリニウム箔を用いた照射も行って、熱および熱外中性子による反応率の寄与をより分けた。ガドリニウムの厚さから、カットオフ・エネルギーは0.133eVに設定した。ニオブ試料中に含まれている不純物により生成される$$^{182}$$Taの放射能を減衰させるために、約2年間ニオブ試料を冷却した。$$gamma$$線スペクトロスコピーにより照射されたニオブ試料およびモニタの生成放射能を測定した。Westcottコンベンションに基づいて解析を行い、$$sigma$$$$_{0}$$およびI$$_{0}$$を、それぞれ1.11$$pm$$0.04barnおよび10.5$$pm$$0.6barnと導出することができた。$$gamma$$線測定の後に、ニオブ試料の質量分析を行い、反応率を導出した。$$gamma$$線スペクトロスコピーと質量分析で得られたデータを組み合わせることにより、$$^{94}$$Nbの半減期を、(2.00$$pm$$0.15)$$times$$10$$^{4}$$年と導出することができた。

論文

Development of a neutron beam monitor with a thin plastic scintillator for nuclear data measurement using spallation neutron source

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

https://doi.org/10.1080/00223131.2022.2067598
 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 $$^{6}$$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.

論文

$$^{241}$$Am neutron capture cross section measurement and resonance analysis

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*; 児玉 有*; 中野 秀仁*; 佐藤 八起*

JAEA-Conf 2022-001, p.91 - 96, 2022/11

https://doi.org/10.11484/jaea-conf-2022-001

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 $$^{241}$$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 $$^{241}$$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 $$^{241}$$Am at the energy of 23.5 keV was determined relative to the $$^{197}$$Au yield obtained from a measurement using the same Au sample. Moreover, early-stage results of a resonance analysis of the $$^{241}$$Am capture resonances are also presented.

論文

Thermal-neutron capture cross-section measurements of neptunium-237 with graphite thermal column in KUR

中村 詔司; 芝原 雄司*; 遠藤 駿典; 木村 敦

Journal of Nuclear Science and Technology, 59(11), p.1388 - 1398, 2022/11

https://doi.org/10.1080/00223131.2022.2058639
 被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)

本研究は、放射性核種の$$^{237}$$Npを取り上げて、よく熱化された中性子場を用いて放射化法により$$^{237}$$Npの熱中性子捕獲断面積を測定した。$$^{237}$$Npの標準溶液を、照射試料に用いた。照射位置の中性子束は、$$^{45}$$Sc, $$^{59}$$Co, $$^{98}$$Mo, $$^{181}$$Taそして$$^{197}$$Auを、中性子束モニタに使用した。$$^{237}$$Np試料とモニタを一緒に、京都大学研究炉の黒鉛照射設備にて30分間照射した。同様の照射を2回繰り返した。照射後に、$$^{237}$$Np試料を、それと放射平衡の関係にある$$^{233}$$Paからの312keVガンマ線を測定して定量した。$$^{237}$$Npの反応率を、生成された$$^{238}$$Npから放出されるガンマ線の収量から求めた。$$^{237}$$Npの熱中性子捕獲断面積は、2回照射の結果の加重平均を取って173.8$$pm$$4.4barnと導出された。この結果は、飛行時間法により測定されたデータと、誤差の範囲で一致した。

論文

Materials science and fuel technologies of uranium and plutonium mixed oxide

加藤 正人; 町田 昌彦; 廣岡 瞬; 中道 晋哉; 生澤 佳久; 中村 博樹; 小林 恵太; 小澤 隆之; 前田 宏治; 佐々木 新治; et al.

Materials Science and Fuel Technologies of Uranium and Plutonium mixed Oxide, 171 Pages, 2022/10

https://doi.org/10.1201/9781003298205

プルトニウム燃料を使用した革新的で先進的な原子炉が各国で開発されている。新しい核燃料を開発するためには、照射試験が不可欠であり、核燃料の性能と安全性を実証する必要がある。照射試験を補完する技術として、照射挙動を正確にシミュレートする技術を開発できれば、核燃料の研究開発にかかるコスト,時間,労力を大幅に削減でき、核燃料の照射挙動をシミュレーションすることで、安全性と信頼性を大幅に向上させることができる。核燃料の性能を評価するためには、高温での燃料の物理的および化学的性質を知る必要がある。そして、照射中に発生するさまざまな現象を記述した行動モデルの開発が不可欠である。以前の研究開発では、モデル開発の多くの部分で、フィッティングパラメータを使用した経験的手法が使用されてきた。経験的手法では、データがない領域では非常に異なる結果が得られる可能性がある。したがって、この研究では、燃料の基本的な特性を組成と温度に外挿できる科学的記述モデルを構築し、モデルが適用される照射挙動分析コードの開発を行った。

論文

Measurements of thermal-neutron capture cross-section of the $$^{237}$$Np(n, $$gamma$$) reaction with TC-Pn in KUR

中村 詔司; 遠藤 駿典; 木村 敦; 芝原 雄司*

KURNS Progress Report 2021, P. 93, 2022/07

https://www.rri.kyoto-u.ac.jp/PUB/report/PR/ProgRep2021/ProgRep2021.html

核廃棄物中のマイナーアクチニドの核変換の観点から、本研究は$$^{237}$$Npを選定して、その熱中性子捕獲断面積を、良く熱化された中性子場を用いて放射化法により測定した。$$^{237}$$Np標準溶液を試料に使用した。熱中性子場は、中性子束モニタ$$^{45}$$Sc, $$^{59}$$Co, $$^{98}$$Mo, $$^{181}$$Taと$$^{197}$$Auを用いて測定した。$$^{237}$$Np試料は、モニタと一緒に、京大炉の黒鉛照射設備にて30分間照射した。結果の再現性を確認するために、同様の照射を繰り返した。照射後、$$^{237}$$Np試料は、$$^{237}$$Npと放射平衡の関係にある$$^{233}$$Paからの312-keVガンマ線を用いて定量した。$$^{237}$$Npの反応率は、生成された$$^{238}$$Npから放出されるガンマ線のピークカウント,検出効率,実験条件を用いて求めた。得られた反応率を熱中性子束で割り込むことで、$$^{237}$$Npの熱中性子捕獲断面積を173.8$$pm$$4.7 barnと導出した。この結果は、飛行時間測定法で得られた報告値と不確かさの範囲内で一致した。

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

https://doi.org/10.1038/s41598-022-08594-2
 被引用回数：1 パーセンタイル：48.43(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

KeV-neutron capture cross-section measurement of $$^{197}$$Au with a Cr-filtered neutron beam at the ANNRI beamline of MLF/J-PARC

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*; 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

https://doi.org/10.1080/00223131.2021.1997666
 被引用回数：1 パーセンタイル：27.15(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 $$^{197}$$Au. The energy range of the neutron filtering system at ANNRI was extended through the use of 15 cm of $$^{nat}$$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 $$^{nat}$$Cr filter assembly was evaluated by means of experimental capture and transmission analyses, together with the use of Monte-Carlo simulations. The present $$^{197}$$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.

論文

Drastic change in magnetic anisotropy of UTe$$_2$$ under pressure revealed by $$^{125}$$Te-NMR

金城 克樹*; 藤林 裕己*; 仲嶺 元輝*; 北川 俊作*; 石田 憲二*; 徳永 陽; 酒井 宏典; 神戸 振作; 仲村 愛*; 清水 悠晴*; et al.

Physical Review B, 105(14), p.L140502_1 - L140502_5, 2022/04

https://doi.org/10.1103/PhysRevB.105.L140502
 被引用回数：3 パーセンタイル：70.67(Materials Science, Multidisciplinary)

To investigate the normal-state magnetic properties of UTe$$_2$$ under pressure, we perform $$^{125}$$Te nuclear magnetic resonance (NMR) measurements up to 2 GPa. Below 1.2 GPa, the b-axis NMR Knight shift shows a broad maximum at the so-called $$T_{chi, max}$$ on cooling, which is consistent with the magnetization measurement under pressure. $$T_{chi, max}$$ decreases with increasing pressure and disappears at the critical pressure $$P_c$$= 1.7 GPa, above which superconductivity is destroyed.

論文

Neutron filtering system for fast neutron cross-section measurement 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

https://doi.org/10.11484/jaea-conf-2021-001

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 $$^{197}$$Au at the filtered energies of 24, 54 and 144 keV are also presented using the NaI(Tl) spectrometer alongside the neutron filtering system.

論文

Development of a neutron beam monitor for nuclear data measurement using spallation neutron source

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

https://doi.org/10.11484/jaea-conf-2021-001

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 $$^{6}$$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 $$^{6}$$LiF foil, the plastic scintillator, and photomultiplier tube (PMT) was designed. The optimal thickness of the $$^{6}$$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 $$^{6}$$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.

論文

A New method to reduce systematic uncertainties of capture cross section measurement using a sample rotation system

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

https://doi.org/10.11484/jaea-conf-2021-001

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 $$gamma$$-ray from the $$^{10}B(n,alphagamma)^{7}Li$$ 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 $$gamma$$-ray from the $$^{10}B(n,alphagamma)^{7}Li$$ 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 $$^{10}B(n,alphagamma)^{7}Li$$ 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.

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

https://doi.org/10.1080/00223131.2021.1970040
 被引用回数：1 パーセンタイル：27.15(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

Slow electronic dynamics in the paramagnetic state of UTe$$_2$$

徳永 陽; 酒井 宏典; 神戸 振作; 芳賀 芳範; 常盤 欣文; Opletal, P.; 藤林 裕己*; 金城 克樹*; 北川 俊作*; 石田 憲二*; et al.

Journal of the Physical Society of Japan, 91(2), p.023707_1 - 023707_5, 2022/02

https://doi.org/10.7566/JPSJ.91.023707
 被引用回数：7 パーセンタイル：95.28(Physics, Multidisciplinary)

ウラン系の強磁性超伝導体で議論されてきた、「強磁性ゆらぎによるスピン三重項超伝導対の形成」および「強磁性ゆらぎを介した磁場による対形成引力の制御」というコンセプトがUTe$$_2$$においても成り立つことを期待させる。しかしその一方、$$_2$$では静的な強磁性秩序は存在せず、低温の磁気状態がこれまでのウラン系強磁性超伝導体にどこまで近いのかという点については疑問を持たれていた。実際、最近の中性子散乱実験では、比較的高温側から反強磁性に近いq=0.57という波数を持った磁気ゆらぎの発達が示されている。本研究では$$^{125}$$Te-NMR実験により低温で非常に遅いゆっくりとした揺らぎが発達する様子を捉えることに成功した。このことはこの系の低温における強い相関の発達を示唆している。

論文

Neutron total and capture cross-section measurements of $$^{155}$$Gd and $$^{157}$$Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC$$cdot$$MLF$$cdot$$ANNRI

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, 19 Pages, 2022/00

https://doi.org/10.1080/00223131.2022.2134224
 被引用回数：1 パーセンタイル：62.84(Nuclear Science & Technology)

Neutron total and capture cross-section measurements of $$^{155}$$Gd and $$^{157}$$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$$pm$$1.7 and 251.9$$pm$$4.6 kilobarn for $$^{155}$$Gd and $$^{157}$$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 59.0$$pm$$2.5 and 247.4$$pm$$3.9 kilobarn for $$^{155}$$Gd and $$^{157}$$Gd, respectively. The present total and capture cross sections agree well within the standard deviations. The results for $$^{155}$$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 $$^{157}$$Gd agreed with the evaluated data in JENDL-4.0 and the experimental data by M${o}$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.

論文

$$^{241}$$Am neutron capture cross section in the keV region using Si and Fe-filtered neutron beams

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*; 児玉 有*; 中野 秀仁*

Journal of Nuclear Science and Technology, 11 Pages, 2022/00

https://doi.org/10.1080/00223131.2022.2116496
 被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)

The neutron capture cross-section of $$^{241}$$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 $$^{nat}$$Fe and $$^{nat}$$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 $$^{241}$$Am results were obtained relative to the $$^{197}$$Au neutron capture yield by applying the total energy detection principle together with the pulse-height weighting technique. The $$^{241}$$Am neutron capture cross section was determined as 2.72 $$pm$$ 0.29 b at 23.5 keV, 2.14 $$pm$$ 0.26 b at 51.5 keV and 1.32 $$pm$$ 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.

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