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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, 60(6), p.678 - 696, 2023/06

 被引用回数:2 パーセンタイル:53.91(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

Fast-neutron capture cross section data measurement of minor actinides for development of nuclear transmutation systems

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 $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$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 $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$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.

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

 被引用回数:1 パーセンタイル:16.35(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

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

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

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

 被引用回数:5 パーセンタイル:65.59(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

Speciation on the reaction of uranium and zirconium oxides treated under oxidizing and reducing atmospheres

上原 章寛*; 秋山 大輔*; 池田 篤史; 沼子 千弥*; 寺田 靖子*; 新田 清文*; 伊奈 稔哲*; 武田 志乃*; 桐島 陽*; 佐藤 修彰*

Journal of Nuclear Materials, 559, p.153422_1 - 153422_11, 2022/02

 被引用回数:2 パーセンタイル:53.91(Materials Science, Multidisciplinary)

The reaction products were analysed by a combination of powder X-ray diffraction (PXRD) and X-ray absorption spectroscopic measurements of the U L$$_{rm III}$$- and Zr K-edges. Under an oxidizing atmosphere, the formation of U$$_{3}$$O$$_{8}$$ and U$$_{2}$$Zr$$_{5}$$O$$_{15}$$ was observed in equilibrium with UO$$_{2}$$, monoclinic-ZrO$$_{2}$$, and tetragonal-ZrO$$_{2}$$. However, when O$$_{2}$$ gas was purged through the reaction tube during the cooling process to room temperature, pentavalent U in ZrU$$_{2}$$O$$_{7}$$ was produced by the oxidation of solid solution UO$$_{2}$$ formed at $$>$$ 1774 K during the temperature dropped at $$<$$ 1473 K. Under the inert atmosphere, mixed oxides of uranium were found to form at $$>$$ 1673 K due to a low concentration of O$$_{2}$$ impurity with the Ar gas. This study can pave the way for understanding the interaction between the nuclear fuels and the cladding materials in damaged reactors enabling further simulation of possible decontamination procedures.

論文

Measurements of the neutron capture cross section of $$^{243}$$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:4 パーセンタイル:56.94(Nuclear Science & Technology)

The neutron capture cross section of $$^{243}$$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 $$gamma$$-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 $$^{197}$$Au of JENDL-4.0. The neutron capture cross section of $$^{243}$$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.

論文

Neutron beam filter system for fast neutron cross-section measurement 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*; 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:4 パーセンタイル:57.13(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.

論文

Neutron capture cross section measurement of minor actinides in fast neutron energy region for study on nuclear transmutation system

片渕 竜也*; 堀 順一*; 岩本 信之; 岩本 修; 木村 敦; 中村 詔司; 芝原 雄司*; 寺田 和司*; 登坂 健一*; 遠藤 駿典; et al.

JAEA-Conf 2020-001, p.5 - 9, 2020/12

A research project entitled "Study on accuracy improvement of fast-neutron capture reaction data of long-lived MAs for development of nuclear transmutation systems" has been ongoing since 2017. The project aims at improving accuracy of neutron capture cross sections of long-lived minor actinides (MAs; $$^{237}$$Np and $$^{241,243}$$Am) in the fast neutron energy region which are very important for development of nuclear transmutation systems. In order to improve the capture reaction data of MAs, measurements using an intense pulsed neutron beam from a spallation neutron source of J-PARC are planned. The project consists of four parts: (1) development of neutron beam filter system, (2) cross section measurement, (3) sample characteristic assay, and (4) theoretical study. The filter system is designed to solve a double bunch issue in J-PARC. The sample characteristic assay lowers systematic uncertainties originating the samples. In the theoretical study, a nuclear reaction model is applied to analyzing cross sections and $$gamma$$-ray spectra measured in experiments. The outline of the project and the current progress will be presented.

論文

Fast neutron capture reaction data measurement of minor actinides for development of nuclear transmutation systems

片渕 竜也*; 岩本 修; 堀 順一*; 木村 敦; 岩本 信之; 中村 詔司; 芝原 雄司*; 寺田 和司*; Rovira, G.*; 松浦 翔太*

EPJ Web of Conferences, 239, p.01044_1 - 01044_4, 2020/09

 被引用回数:2 パーセンタイル:86.93(Nuclear Science & Technology)

In 2017, a research project entitled "Study on accuracy improvement of fast-neutron capture reaction data of long-lived MAs for development of nuclear transmutation systems" started as a joint collaboration, including Tokyo Tech, Japan Atomic Energy Agency and Kyoto University. This project focuses on neutron capture reaction of MAs, especially $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$Am, in the fast neutron energy region. The final goal of this project is to improve the neutron capture cross sections of $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$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. In this contribution, the overview of the project and the current progress will be presented.

論文

Neutron capture cross-section measurement and resolved resonance analysis of $$^{237}$$Np

Rovira, G.*; 片渕 竜也*; 登坂 健一*; 松浦 翔太*; 寺田 和司*; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之; 瀬川 麻里子; et al.

Journal of Nuclear Science and Technology, 57(1), p.24 - 39, 2020/01

 被引用回数:10 パーセンタイル:79.13(Nuclear Science & Technology)

The neutron capture cross-section of $$^{237}$$Np has been measured in the neutron energy region of 10 meV to 500 eV. A neutron time-of-flight method was employed using the NaI(Tl) spectrometer in the ANNRI beam-line at the Japanese Proton Accelerator Re-search Complex (J-PARC). The experimental capture yield was derived using the pulse-height weighting technique and an energy dependent cross-section was obtained relative to the incident neutron spectrum derived from a $$^{10}$$B(n, $$alpha$$)$$^{7}$$Li reaction yield. The absolute cross-section was determined by normalizing the results to JENDL-4.0 cross-section data at the first resonance of $$^{237}$$Np. The thermal cross-section was measured to be 177.6 $$pm$$ 3.8 b. The resolved resonance region was analyzed with the REFIT code.

論文

Neutron capture reaction data measurement of minor actinides in fast neutron energy region for study on nuclear transmutation system

片渕 竜也*; 岩本 修; 堀 順一*; 岩本 信之; 木村 敦; 中村 詔司; 芝原 雄司*; 寺田 和司*

JAEA-Conf 2019-001, p.193 - 197, 2019/11

A research project entitled "Study on improvement of neutron capture reaction data accuracies of long-lived minor actinides in fast neutron energy region for development of nuclear transmutation systems" started in 2017. The project aims at improving accuracies of neutron capture cross section of long-lived minor actinides ($$^{237}$$Np, $$^{241}$$Am, $$^{243}$$Am) in the fast neutron energy region which are very important for development of nuclear transmutation systems. In order to improve the capture reaction data of MA, measurement using an intense pulsed neutron beam from a spallation neutron source of the Japan Proton Accelerator Research Complex (J-PARC) is planned. The neutron beam filter is designed to solve the so-called double bunch issue of a neutron beam in J-PARC. This allows for measuring neutron capture cross sections using the high-intensity neutron beam of J-PARC. The outline of the project and the current progress will be presented.

論文

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

 被引用回数:14 パーセンタイル:84.54(Nuclear Science & Technology)

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.

論文

Measurements of gamma-ray emission probabilities in the decay of americium-244g

中村 詔司; 寺田 和司*; 木村 敦; 中尾 太郎*; 岩本 修; 原田 秀郎; 上原 章寛*; 高宮 幸一*; 藤井 俊行*

Journal of Nuclear Science and Technology, 56(1), p.123 - 129, 2019/01

 被引用回数:1 パーセンタイル:11.15(Nuclear Science & Technology)

$$gamma$$線計測により同位体を定量したり、断面積を求める際に、正確な$$gamma$$線放出率のデータが、必要になってくる。$$^{243}$$Amは、重要なマイナーアクチノイド核種の一つであり、中性子捕獲後に$$^{244}$$Amを生成する。$$^{244}$$Amの基底状態から放出される744-keV$$gamma$$線は66%と比較的大きな$$gamma$$線放出率を持つけれども、その誤差は29%と大きい。$$gamma$$線放出率の誤差は、放射化法による中性子捕獲断面積測定において、系統誤差の主要因となる。そこで、放射化法と$$^{244}$$Cmのレベルを調べることにより、$$gamma$$線放出率を測定した。本研究により、744-keV$$gamma$$線の放出率を、66.5$$pm$$1.1%と、相対誤差29%から2%に低減して導出することができた。

報告書

北朝鮮による地下核実験に対する大気拡散予測の対応活動

石崎 修平; 早川 剛; 都築 克紀; 寺田 宏明; 外川 織彦

JAEA-Technology 2018-007, 43 Pages, 2018/10

JAEA-Technology-2018-007.pdf:5.67MB

北朝鮮が地下核実験を実施した際、原子力緊急時支援・研修センターは、原子力規制庁からの要請に基づき、国による対応への支援活動として、原子力基礎工学研究センターの協力を得て、WSPEEDI-IIシステムを用いて放射性物質の大気拡散予測計算を実施し、予測情報を原子力規制庁に提出する。本報告書は、北朝鮮による地下核実験に対する国及び原子力機構の対応体制を説明するとともに、平成28年9月及び平成29年9月に実施された5回目及び6回目の地下核実験を主たる対象として、原子力緊急時支援・研修センターが実施した大気拡散予測に関する一連の対応活動を記述する。さらに、予測計算に使用した計算プログラムシステムの概要について説明するとともに、北朝鮮地下核実験対応における今後の計画と課題を記述する。

論文

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

AA2017-0628.pdf:2.06MB

 被引用回数:18 パーセンタイル:88.27(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.

論文

Resonance analysis of cross section data measured by J-PARC/MLF using the modified REFIT code

水山 一仁; 岩本 信之; 岩本 修; 寺田 和司; 中尾 太郎

JAEA-Conf 2017-001, p.163 - 168, 2018/01

In the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)", the cross section data of MAs ($$^{241,243}$$Am, $$^{237}$$Np) have been measured at neutron time-of-flight (TOF) beam line ANNRI installed at J-PARC/MLF. The high precision data is expected even in the case of small amount sample because the reaction rates are strongly increased by the high intensity pulsed neutron beam of J-PARC/MLF. We are going to analyze those cross section data by using the least-squares multilevel R-matrix code REFIT. For precise analysis of the cross section data measured by ANNRI, it is necessary to take into account the energy resolution function. In this study, we therefore adopt the modified version of REFIT which treats the energy resolution function for ANNRI. The precise energy calibration is also important. We performed the resonance analysis of the neutron total and capture cross section data of $$^{197}$$Au measured by ANNRI under the same operational condition of J-PARC/MLF to fix parameters related to energy calibration.

論文

Technical developments for accurate determination of amount of samples used for TOF measurements

寺田 和司; 中尾 太郎; 中村 詔司; 木村 敦; 岩本 修; 原田 秀郎; 高宮 幸一*; 堀 順一*

EPJ Web of Conferences, 146, p.03019_1 - 03019_4, 2017/09

 被引用回数:3 パーセンタイル:86.43(Nuclear Science & Technology)

革新炉や核変換処理の研究開発のため、高精度なマイナーアクチニド(MA)の中性子捕獲断面積が求められている。しかし、現状の精度と要求される精度の間には倍以上の隔たりがある。そこで、MAの断面積精度向上を目的として「マイナーアクチニドの中性子核データ精度向上に係る研究開発」が進められている。精度の良い断面積を得るためには、測定に用いるMA試料のサンプル量を正確に決めることが必要不可欠である。そのため、本プロジェクトの研究課題の一つとして、$$gamma$$線分光法とカロリーメーターを用いた熱測定という2つの異なる手法を用いてサンプル量の高精度決定のための技術開発を進めている。$$gamma$$線分光法では、サンプルからの崩壊$$gamma$$線測定による定量精度向上のために、MAの崩壊$$gamma$$線の高精度測定を実施し、$$gamma$$線放出率を2%以下の精度で決定した。カロリーメーターを用いた熱測定では、MAのQ値が精度よく分かっているため崩壊熱を精密に測定することでMAの放射能値を決定することができる。本発表では、これら2つの手法の開発及び得られた結果について発表する。

論文

Developments of a new data acquisition system at ANNRI

中尾 太郎; 寺田 和司; 木村 敦; 中村 詔司; 岩本 修; 原田 秀郎; 片渕 竜也*; 井頭 政之*; 堀 順一*

EPJ Web of Conferences, 146, p.03021_1 - 03021_4, 2017/09

 被引用回数:7 パーセンタイル:96.32(Nuclear Science & Technology)

J-PARC物質・生命科学実験施設ANNRIビームラインのデータ収集系更新作業が行われた。MLFのビームパワーは2008年に比較して2015年には20倍以上となり、ビーム量の増大によりビームラインユーザーはより高統計の実験データを取得できるようになった。ビームパワー増大に対応するため、ANNRIにおけるGe検出器アレイのデータ収集システムが更新された。データ収集システムは同時に、中性子全断面積測定のために整備されているLi glass検出器の信号取得のためにも用いられる予定である。コミッショニング実験が0.1mm厚の金サンプルを用いてJ-PARCの500kW陽子ビームを用いて行われた。捕獲断面積および全断面積測定両方について飛行時間法の適用性が試験された。Ge検出器アレイについて、ADCおよびTDCの非線形性、エネルギー分解能、多チャンネルコインシデンスおよび不感時間の性能が測定された。Ge検出器の不感時間は従来のデータ収集システムに比較して、少しのエネルギー分解能劣化を許容すれば1/4になっていた。

論文

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, 146, p.11001_1 - 11001_6, 2017/09

 被引用回数:2 パーセンタイル:78.04(Nuclear Science & Technology)

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.

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