検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年
検索結果: 1243 件中 1件目~20件目を表示

発表形式

Initialising ...

選択項目を絞り込む

掲載資料名

Initialising ...

発表会議名

Initialising ...

筆頭著者名

Initialising ...

キーワード

Initialising ...

使用言語

Initialising ...

発行年

Initialising ...

開催年

Initialising ...

選択した検索結果をダウンロード

論文

Development of failure mitigation technologies for improving resilience of nuclear structures, 1; Failure mitigation by passive safety structures without catastrophic failure

笠原 直人*; 山野 秀将; 中村 いずみ*; 出町 和之*; 佐藤 拓哉*; 一宮 正和*

Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet), 8 Pages, 2024/03

本研究では、受動安全構造を適用することによって破損拡大抑制方法を提案する。受動安全構造のアイデアを超高温条件および過大地震時の次世代高速炉に適用した。

論文

J-PARC MRのための横方向不安定性の記述に向けたシミュレーションの構築

吉村 宣倖*; 外山 毅*; 菖蒲田 義博; 中村 剛*; 大見 和史*; 小林 愛音*; 岡田 雅之*; 佐藤 洋一*; 中家 剛*

Proceedings of 20th Annual Meeting of Particle Accelerator Society of Japan (インターネット), p.260 - 264, 2023/11

-PARCメインリング(MR)の出力は1.3MWに増強される予定である。そのために、イントラバンチフィードバックシステム(IBFB)を最大約200MHzまでの高い周波数に対応できるようにアップグレードする必要がある。このアップグレード後の性能を評価し、最適なパラメータを理解するために、現在、必要なコンポーネントを含む粒子トラッキングシミュレーションを開発している。その結果、色収差によって引き起こされるビームのリコヒーレンス時間を、トラッキングシミュレーションと実験との間で比較し、それが単純なシミュレーションでは説明できないことを確認した。現在、この結果を説明するメカニズムを調査しているが、縦方向のインピーダンスの効果のみでは、この実験結果を説明できないことがわかった。

論文

超高真空材料プロセス研究のためのガス精密制御の自動化; 表面反応の放射光リアルタイム観察への応用

中村 孝史*; 山本 幸男*; 荒川 正和*; 丸山 晃生*; 吉越 章隆

産業応用工学会論文誌, 11(2), p.109 - 114, 2023/09

SPring-8のBL23SUに設置された表面化学実験ステーションは、放射光軟X線を使って様々な機能性材料の表面および界面の研究に利用されている。固体表面とガスとの化学反応の理解を進めるためには、ガスの精密流量制御が必須である。本論文では、超高真空(分子流領域)におけるガスと表面の反応の実験精度および再現性を改善するための自動ガス流量コンピュター制御システムを報告する。ガス圧力制御のために、スローリークバルブのフィードバック制御システムを開発した。開発したシステムによって、装置エキスパートの実験者と同等以上の反応実験が可能となった。

論文

Termination of downward-oriented gamma-ray glow by normal-polarity in-cloud discharge activity

和田 有希*; Wu, T.*; Wang, D.*; 榎戸 輝揚*; 中澤 知洋*; 森本 健志*; 中村 佳敬*; 篠田 太郎*; 土屋 晴文

Journal of Geophysical Research; Atmospheres, 128(15), p.e2023JD038606_1 - e2023JD038606_9, 2023/08

 被引用回数:2 パーセンタイル:58.15(Meteorology & Atmospheric Sciences)

A gamma-ray glow, a minute-lasting burst of high-energy photons from a thundercloud, was detected by ground-based apparatus at Kanazawa University, Japan, in a winter thunderstorm on 18 December 2018. The gamma-ray glow was quenched by a lightning flash within a brief time window of 40 ms. The lightning flash produced several low-frequency (LF) E-change pulses that were temporally coincident withthe termination of the gamma-ray glow, and that were located within 0.5 km from the observation site by the Fast Antenna Lightning Mapping Array. The LF pulses had the same polarity as a positive cloud-to-ground current and a normal-polarity in-cloud current. Since this polarity is against the upward electric field for producing the gamma-ray glow (accelerating electrons to the ground), we infer that the glow was terminated by a normal-polarity in-cloud discharge activity between a middle negative layer and an upper positive layer.

論文

Citizen science observation of a gamma-ray glow associated with the initiation of a lightning flash

鶴見 美和*; 榎戸 輝掲*; 一方井 祐子*; Wu, T.*; Wang, D.*; 篠田 太郎*; 中澤 知洋*; 辻 直樹*; Diniz, G.*; 片岡 淳*; et al.

Geophysical Research Letters, 50(13), p.e2023GL103612_1 - e2023GL103612_9, 2023/07

 被引用回数:0 パーセンタイル:0(Geosciences, Multidisciplinary)

Gamma-ray glows are observational evidence of relativistic electron acceleration due to the electric field in thunderclouds. However, it is yet to be understood whether such relativistic electrons contribute to the initiation of lightning discharges. To tackle this question, we started the citizen science "Thundercloud Project," where we map radiation measurements of glows from winter thunderclouds along Japan's sea coast area. We developed and deployed 58 compact gamma-ray monitors at the end of 2021. On 30 December 2021, five monitors simultaneously detected a glow with its radiation distribution horizontally extending for 2 km. The glow terminated coinciding with a lightning flash at 04:08:34 JST, which was recorded by the two radio-band lightning mapping systems, FALMA and DALMA. The initial discharges during the preliminary breakdown started above the glow, that is, in vicinity of the electron acceleration site. This result provides one example of possible connections between electron acceleration and lightning initiation.

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

 被引用回数:1 パーセンタイル:54.26(Chemistry, Physical)

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

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

Development of nondestructive elemental analysis system for Hayabusa2 samples using muonic X-rays

大澤 崇人; 長澤 俊作*; 二宮 和彦*; 高橋 忠幸*; 中村 智樹*; 和田 大雅*; 谷口 秋洋*; 梅垣 いづみ*; 久保 謙哉*; 寺田 健太郎*; et al.

ACS Earth and Space Chemistry (Internet), 7(4), p.699 - 711, 2023/04

 被引用回数:4 パーセンタイル:93.95(Chemistry, Multidisciplinary)

小惑星試料中の炭素をはじめとする主要元素の濃度は、地球上の生命の誕生や太陽系の進化について非常に重要な情報を与えてくれる。ミュオンX線を用いた元素分析は、固体物質の元素組成を決定する最も優れた分析方法の一つであり、特にバルク試料中の軽元素濃度を非破壊で測定できる唯一の方法である。我々は、探査機「はやぶさ2」が小惑星リュウグウから回収した貴重な微小試料中の炭素などの主要元素の濃度を測定するために、ミュオンX線を用いた新しい分析システムを開発した。この分析システムは、ステンレス製の分析チャンバー、クリーンな環境で小惑星サンプルを操作するためのアクリル製のグローブボックス、分析チャンバーを囲むように配置されたGe半導体検出器から構成されている。測定に重要なバックグラウンドレベルを含め、分析装置の性能は初期から後期まで大幅に向上した。フィージビリティスタディの結果、最新型のミュオンX線分析装置は、「はやぶさ2」のサンプルモデル中の炭素濃度を6日間の測定で10%以下の不確かさで決定できることがわかった。

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

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

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.

報告書

研究施設等廃棄物のトレンチ埋設施設におけるスカイシャイン線量評価

中村 美月; 出雲 沙理; 小川 理那; 仲田 久和; 天澤 弘也; 坂井 章浩

JAEA-Technology 2022-025, 73 Pages, 2022/12

JAEA-Technology-2022-025.pdf:1.64MB

日本原子力研究開発機構は、研究施設等廃棄物の埋設処分事業の実施主体として、浅地中処分の実施に向けた検討を進めている。研究施設等廃棄物の埋設処分事業では埋設施設の操業中の安全評価として、ピット施設、トレンチ施設及び受入検査施設からの直接$$gamma$$線及びスカイシャイン$$gamma$$線による敷地境界での実効線量が、「第二種廃棄物埋設施設の位置、構造及び設備の基準に関する規則の解釈」に規定された50$$mu$$Sv/y以下となることを示す必要がある。直接$$gamma$$線及びスカイシャイン$$gamma$$線による実効線量が50$$mu$$Sv/y以下とするためには、各施設から敷地境界までの距離を120m以上とすることが、概念設計の結果に基づき立地基準案では示された。一方、令和元年に埋設対象廃棄体の物量調査を行い、その結果、トレンチ処分対象の廃棄体等本数が概念設計時に比べて増加し、トレンチ施設に係る施設規模等の設計が変更された。そこで、本報告書では2次元Sn輸送計算コードDOT3.5を用いて、設計変更後のトレンチ施設からの距離に応じた敷地境界でのスカイシャイン線量評価の感度解析を実施した。各トレンチ施設1基あたりの評価及び各トレンチ施設の重畳評価の結果、どちらの評価結果においても各施設から120m離れた敷地境界でのスカイシャイン$$gamma$$線による実効線量が50$$mu$$Sv/y以下となることを確認した。

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

 被引用回数:1 パーセンタイル:31.61(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

Possible future upgrades of the direct-geometry chopper spectrometer 4SEASONS

梶本 亮一; 中村 充孝; 蒲沢 和也*; 稲村 泰弘; 飯田 一樹*; 池内 和彦*; 石角 元志*

EPJ Web of Conferences, 272, p.02007_1 - 02007_8, 2022/11

4SEASONS is a direct geometry time-of-flight spectrometer installed in the Materials and Life Science Experimental Facility, the Japan Proton Accelerator Research Complex. It is used to study atomic andspin dynamics in the energy range of $$10^0$$ meV to $$10^2$$ meV. Since more than a decade has crossed after the first inelastic scattering experiment, it is essential to consider upgrading the instrument to improve its flexibility and performance. In this paper, we discuss the possible medium-term upgrades of key components of the instrument like the chopper system, which are achievable with the current technology and at reasonable cost. Herein, we demonstrated that 4SEASONS can improve the energy resolution by a factor of two, remove frame overlap of adjacent incident energies, significantly improve the asymmetry in the pulse shape, and increase the flux by a factor of $$sim$$1.5, without major technical difficulties.

論文

Harmless treatment of radioactive liquid wastes for safe storage in systematic treatment of radioactive liquid waste for decommissioning project

中原 将海; 渡部 創; 粟飯原 はるか; 高畠 容子; 荒井 陽一; 小木 浩通*; 中村 雅弘; 柴田 淳広; 野村 和則

Proceedings of International Conference on Nuclear Fuel Cycle; Sustainable Energy Beyond the Pandemic (GLOBAL 2022) (Internet), 4 Pages, 2022/07

高レベル放射性物質研究施設において高速炉燃料再処理技術,高レベル放射性廃棄物処分技術,核燃料サイクル技術に関する基礎研究に伴い様々な液体廃棄物が発生している。これらの試験において様々な試薬は使用されており、試験の過程で有害な物質が発生している。これらの放射性液体廃棄物を安全な状態で保管するために分解,溶媒抽出,沈殿,固化処理等により無害化処理に関する研究開発を実施している。本研究では、放射性液体廃棄物の無害化処理に係る研究開発の現状を報告する。

論文

Development plan of failure mitigation technologies for improving resilience of nuclear structures

笠原 直人*; 山野 秀将; 中村 いずみ*; 出町 和之*; 佐藤 拓哉*; 一宮 正和*

Transactions of the 26th International Conference on Structural Mechanics in Reactor Technology (SMiRT-26) (Internet), 8 Pages, 2022/07

破壊制御を利用して、設計想定を超える事象によって破損が生じた場合に、その拡大を抑制する技術の開発を進めている。開発課題として、(1)超高温時の破損拡大抑制技術、(2)課題地震時の破損拡大抑制技術、(3)原子炉構造レジリエンス向上手法の3つの計画を立てた。

報告書

固体高分子電解質水電解法による溶存水素濃度制御装置の開発

中野 寛子; 冬島 拓実; 津口 明*; 中村 和*; 武内 伴照; 竹本 紀之; 井手 広史

JAEA-Technology 2022-007, 34 Pages, 2022/06

JAEA-Technology-2022-007.pdf:3.35MB

軽水炉高温高圧水を模擬した環境における構造材料の応力腐食割れ(SCC)等の現象を把握するため、水質を管理することが重要である。一般的に、材料試験を行うための高温高圧水試験装置の循環水中溶存水素濃度は、純水素ガスや高水素濃度の標準ガスのバブリングにより制御している。しかしながら、この方法では試験装置の設置場所に大掛かりな防爆設備等が必要である。一般的に、水素災害防止のためには、爆発に至る前に漏えい量の制限、水素の排除、電源の遮断、燃焼の抑制等の対策を講じることが求められている。このため、水の電気分解を利用し、循環水中溶存水素濃度を制御できる固体高分子電解質膜を有する溶存水素濃度制御装置の開発に着手した。本開発にあたっては、小型基本実験装置を組立て、固体高分子電解質膜の単体性能及び循環状態における溶存水素濃度変化に関する基本データを取得した。この基本データに基づき、実機の高温高圧水ループ試験装置に設置する溶存水素濃度制御装置を設計した。本報告書は、小型基本実験装置による性能試験結果と溶存水素濃度制御装置の基本設計についてまとめたものである。

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

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

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

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.

1243 件中 1件目~20件目を表示