検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年
検索結果: 417 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

Measurement of 107-MeV proton-induced double-differential neutron yields for iron for research and development of accelerator-driven systems

岩元 大樹; 中野 敬太; 明午 伸一郎; 佐藤 大樹; 岩元 洋介; 石 禎浩*; 上杉 智教*; 栗山 靖敏*; 八島 浩*; 西尾 勝久; et al.

JAEA-Conf 2022-001, p.129 - 133, 2022/11

加速器駆動システム(ADS)の核特性予測精度の向上と京都大学臨界集合体実験装置(KUCA)におけるADS炉物理実験で用いる中性子源情報の取得を目的として、京都大学の固定磁場強集束(FFAG)加速器を用いた核データ測定実験プログラムを開始した。このプログラムの一環として、鉄に対する陽子入射二重微分中性子収量(TTNY)及び断面積(DDX)を測定した。測定では、真空チェンバ内に設置された鉄標的に107MeVの陽子ビームを照射し、核反応によって標的から発生した粒子の信号を、小型の中性子検出器を用いて検出した。検出信号とFFAGキッカー電磁石の信号の時間差から飛行時間(TOF)を求め、ガンマ線の事象を波形弁別法によって除去して中性子事象をカウントすることで中性子のTOFスペクトルを求めた。得られた中性子のTOFスペクトルから、相対論的運動学により鉄標的に対するTTNY及びDDXを求めた。

論文

Integral experiment of $$^{129}$$I(n, $$gamma$$) using fast neutron source in the "YAYOI" reactor

中村 詔司; 藤 暢輔; 木村 敦; 初川 雄一*; 原田 秀郎

Journal of Nuclear Science and Technology, 59(7), p.851 - 865, 2022/07

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

本研究は、東京大学の高速中性子源炉「弥生」を用いて、評価済み核データライブラリーを検証するために放射化法により$$^{129}$$Iの積分実験を行った。$$^{129}$$Iと中性子束モニタを、弥生炉のグローリー孔にて照射した。反応率は、$$^{130}$$Iから放出されるガンマ線の収量から求めた。中性子束モニタの反応率の実験値と計算値との比較から、高速中性子スペクトルの確かさを確認した。$$^{129}$$Iの反応率の実験値を、評価済み核データライブラリーを用いて求めた計算値と比較した。本研究で、評価済みライブラリーJENDL-4.0に採用されている中性子エネルギー10keVから3MeV領域の中性子捕獲断面積データは、18%程、過大評価されていることが分かった。また、本研究の結果は、100keV以下では、Noguere等による報告データを支持した。

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

 被引用回数:0 パーセンタイル:0(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

Investigation of radioactive samples for neutron capture reaction measurements using energy-resolved neutron imaging

瀬川 麻里子; 藤 暢輔; 甲斐 哲也; 木村 敦; 中村 詔司

Annals of Nuclear Energy, 167, p.108828_1 - 108828_5, 2022/03

 被引用回数:0 パーセンタイル:0.02(Nuclear Science & Technology)

To obtain accurate analytical results via neutron-capture reactions, the effects of sample shapes must be considered. However, the estimations of the effects were difficult to verify in some cases such as sealed samples and valuable objects. In this study, the shape effects for sealed radioactive samples were estimated experimentally. The significant localization of the $$^{129}$$I sample was confirmed only by an energy-resolved neutron imaging. It is revealed that the shape effect was necessary to be corrected at the neutron resonance peaks. Consequently, we conclude that the energy-resolved neutron imaging will be quite effective to improve the analytical accuracy.

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:0 パーセンタイル:0.01(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

Measurement of 107-MeV proton-induced double-differential thick target neutron yields for Fe, Pb, and Bi using a fixed-field alternating gradient accelerator at Kyoto University

岩元 大樹; 中野 敬太; 明午 伸一郎; 佐藤 大樹; 岩元 洋介; 杉原 健太; 西尾 勝久; 石 禎浩*; 上杉 智教*; 栗山 靖敏*; et al.

Journal of Nuclear Science and Technology, 15 Pages, 2022/00

 被引用回数:0

加速器駆動核変換システム(ADS)の研究開発及び京都大学臨界実験装置(KUCA)におけるADS未臨界炉物理の基礎研究を目的として、固定磁場強収束(FFAG)加速器を用いて107MeV陽子による鉄、鉛及びビスマス標的に対する二重微分中性子収量(TTNY)を測定した。TTNYは8個の中性子検出器(各検出器は小型のNE213液体有機シンチレータと光電子増倍管より構成される)からなる中性子検出器システムを用いて飛行時間法により得られたものである。測定で得られたTTNYを、粒子・重イオン輸送コードシステム(PHITS)に組み込まれたモンテカルロ法に基づく核破砕反応モデル(INCL4.6/GEM, Bertini/GEM, JQMD/GEM, JQMD/SMM/GEM)及び評価済み高エネルギー核データライブラリ(JENDL-4.0/HE)による計算結果と比較した。JENDL-4.0/HEを含む比較対象のモデルは、検出器角度5度における高エネルギーピークを再現しないなどの特徴的な不一致が見られた。測定で得られたTTNYとPHITSによって評価した20MeV以下のエネルギー及び角度積分中性子収率を比較した結果、INCL4.6/GEMがKUCAにおけるADS炉物理実験のモンテカルロ輸送シミュレーションに適していることが示された。

論文

Integral experiments of technetium-99 using fast-neutron source reactor "YAYOI"

中村 詔司; 初川 雄一*; 木村 敦; 藤 暢輔; 原田 秀郎

Journal of Nuclear Science and Technology, 58(12), p.1318 - 1329, 2021/12

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

本研究は、東大の高速中性子源炉「弥生」を用いて、放射化法により$$^{99}$$Tcの積分実験を行った。$$^{99}$$Tc試料を、気送管システムを用いて照射した。$$^{99}$$Tcの反応率は、$$^{100}$$Tcから放出されるガンマ線を測定して求めた。中性子束は、Au箔を用いてモニタした。本研究における$$^{99}$$Tcの反応率の結果は、JENDL-4.0を支持した。

論文

First demonstration experiment of the neutron rotation method for detecting nuclear material

米田 政夫; 藤 暢輔; 田辺 鴻典*; 北村 康則*; 三澤 毅*

Annals of Nuclear Energy, 159, p.108300_1 - 108300_8, 2021/09

 被引用回数:1 パーセンタイル:39.48(Nuclear Science & Technology)

The rotation method is a novel method for detecting nuclear materials using a neutron source such as californium. In this method, while a neutron source is rotated rapidly nearby a measurement object, neutron measurement is carried out by synchronizing the rotation motion. If the object contains a nuclear material, as the rotation speed increases, the larger deformation of time distribution of neutron counts is observed, which in turn resulted to the detection of the nuclear material. In addition to its features of low cost and portability, this method is capable of detecting uranium that emits very few spontaneous fission neutrons. This study presents the fundamental principle of this method and its effectiveness for detecting nuclear materials through the experimental verifications.

論文

Development of an integrated active neutron non-destructive analysis system; Active-N

藤 暢輔; 大図 章; 土屋 晴文; 古高 和禎; 北谷 文人; 米田 政夫; 前田 亮; 小泉 光生

Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 8 Pages, 2021/08

Since neutrons have exceptional ability to penetrate high-density materials and can induce fission, they are used in non-destructive analysis such as, Differential Die-Away Analysis (DDA), Prompt Gamma-ray Analysis (PGA) and Neutron Resonance Transmission Analysis (NRTA). The different analytical methods give us complementary information, which are particularly useful for the quantification of Special Nuclear Materials in highly radioactive nuclear materials, including spent fuel. The Japan Atomic Energy Agency (JAEA) and the Joint Research Centre (JRC) of the European Commission are collaborating to develop an active neutron NDA system for nuclear non-proliferation and nuclear security. In the second phase of the project, an integrated active neutron NDA system: Active-N which enables the simultaneous measurements of DDA, PGA and NRTA has been developed. The DDA detects fission neutrons, and it can determine small amounts of the fissile mass. PGA is utilized for the quantification of neutron absorber and particularly useful for the detection of explosives. NRTA can be used to quantify almost all medium and high-Z elements and considered as one of the most accurate NDA. In this presentation, we will provide an overview of Active-N and report the recent experimental results. This research was implemented under the subsidy for nuclear security promotion of MEXT: Ministry of Education, Culture, Sports, Science and Technology.

論文

The Design and implementation of the PGA measurement system in an integrated Active Neutron non-destructive analysis system, "Active-N"

古高 和禎; 大図 章; 藤 暢輔

Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 9 Pages, 2021/08

We have been developing an integrated active neutron non-destructive analysis system for highly radioactive nuclear materials, "Active-N", using an intense D-T neutron source. The system is composed of the following mutually complementing different measurement systems: Differential Die-away Analysis (DDA), Neutron Resonance Transmission Analysis (NRTA), and Prompt Gamma-ray Analysis (PGA). The former two are for measurements of total amount of fissile material and of isotopic composition, respectively. The purpose of the last one, i.e. PGA measurement system is the detection of explosives contained in e.g., dirty bombs and of chemical warfare agents, as well as of neutron poisons which absorb neutrons and disturb DDA measurements. This report describes mainly the PGA measurement system. In the PGA measurement system, to resolve individual gamma-ray peaks, a Ge detector is utilized. It is well known that irradiation of fast neutrons ($$gesim10$$ keV) to Ge detectors cause damages to the detectors and gradually worsen their resolution, and finally make them unusable without a laborious treatment. Therefore, it is essential to shield the PGA detector against the neutrons from the D-T neutron generator. In addition, to reduce background gamma rays from the materials used for the DDA system, they should also be carefully chosen. In order to design an appropriate neutron shield for the PGA measurement system and diminish the sources of the background gamma rays, simulation study was done using a particle transport code system PHITS. Based on the results, a shielding for the PGA measurement system has been designed which reduces the number of damaging neutrons by an order of magnitude. The Active-N system which incorporates the PGA measurement system equipped with the neutron shielding, has been installed at NUCEF facility in JAEA Tokai. This research was implemented under the subsidy for nuclear security promotion from MEXT.

論文

Nondestructive quantitative analysis of difficult-to-measure radionuclides $$^{107}$$Pd and $$^{99}$$Tc

藤 暢輔; 瀬川 麻里子; 前田 亮; 常山 正幸*; 木村 敦; 中村 詔司; 遠藤 駿典; 海老原 充*

Analytical Chemistry, 93(28), p.9771 - 9777, 2021/07

 被引用回数:2 パーセンタイル:43.65(Chemistry, Analytical)

Considering the expanding demand for nuclear waste management of the spent nuclear fuel materials in near future, a non-destructive analytical scheme applicable to the most difficult-to-measure nuclide of $$^{107}$$Pd, which emits no decay gamma-rays and whose half-life is too long to be decayed out during a human lifetime, was designed. The scheme consists of a sophisticated instrument capable of the detection of gamma-rays by Ge detectors coupled with time-of-flight measurement of neutrons and a high-intensity pulsed neutron beam, and can simultaneously perform TOF-coupled prompt gamma-ray analysis (TOF-PGA) as well as PGA and NRCA. An analytical capability was evaluated by applying to simulated samples of the Tc-platinum group metals (Tc-PGMs) obtained by the group partitioning process of spent nuclear fuels, which contain not only $$^{107}$$Pd but also $$^{99}$$Tc and another difficult-to-measure fission product. It was confirmed that, although PGA and NRCA could accurately analyze both nuclides in individual single substances, only TOF-PGA can analyze $$^{107}$$Pd as well as $$^{99}$$Tc in the Tc-PGMs simulated sample. The TOF-PGA measurement technique can be widely used for the non-destructive analysis of $$^{107}$$Pd and $$^{99}$$Tc in nuclear wastes.

論文

Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC

川瀬 頌一郎*; 木村 敦; 原田 秀郎; 岩本 信之; 岩本 修; 中村 詔司; 瀬川 麻里子; 藤 暢輔

Journal of Nuclear Science and Technology, 58(7), p.764 - 786, 2021/07

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

The neutron capture cross sections of $$^{244}$$Cm and $$^{246}$$Cm were measured for the neutron energy range of 1-1000 eV via the neutron time-of-flight method with ANNRI at MLF of the J-PARC. The world's most intense neutron pulses from the Japan Spallation Neutron Source enable the accurate measurement of neutron capture cross sections. Besides, single-bunched neutron pulses allow the analysis in a higher neutron energy region than the previous measurement at ANNRI. The resonance analyses were performed up to 1000 eV by using a resonance shape analysis code REFIT. The spectra of prompt gamma-rays from neutron capture reactions of $$^{244}$$Cm and $$^{246}$$Cm were also obtained, and 43 and 10 prompt gamma-ray peaks from $$^{244}$$Cm(n,$$gamma$$) and $$^{246}$$Cm(n,$$gamma$$) reactions were newly observed, respectively.

論文

Isomer production ratio of the $$^{112}$$Cd($$n,gamma$$)$$^{113}$$Cd reaction in an $$s$$-process branching point

早川 岳人*; 藤 暢輔; 木村 敦; 中村 詔司; 静間 俊行*; 岩本 信之; 千葉 敏*; 梶野 敏貴*

Physical Review C, 103(4), p.045801_1 - 045801_5, 2021/04

 被引用回数:0 パーセンタイル:0.02(Physics, Nuclear)

A $$beta$$-decay unstable isomer with a half-life of 14.1 y at 264 keV in $$^{113}$$Cd is a branching point in the $$s$$ process, from which a weak branch reaches to a rare tin isotope $$^{115}$$Sn whose astrophysical origin has been an open problem. We have measured $$gamma$$ rays decaying to the ground state or the isomer in the $$^{112}$$Cd($$n,gamma$$)$$^{113}$$Cd reaction using high-energy resolution detectors in conjunction with a time-of-flight method. The relative production ratios of the isomer to the total following the neutron capture reactions on $$^{112}$$Cd have been evaluated in an energy region of up to 9 keV, and the spin and parity of several resonances have been assigned.

論文

Feasibility study of PGAA for boride identification in simulated melted core materials

土川 雄介; 阿部 雄太; 大石 佑治*; 甲斐 哲也; 藤 暢輔; 瀬川 麻里子; 前田 亮; 木村 敦; 中村 詔司; 原田 正英; et al.

JPS Conference Proceedings (Internet), 33, p.011074_1 - 011074_6, 2021/03

福島原子力発電所の解体作業では、溶融した燃料棒に含まれるホウ素分布を事前に把握することが重要である。溶融燃料棒の模擬試験体を用意し、ホウ素やホウ化物の含有量を調査する研究が行われてきた。本研究では、その一環として中性子を用いたホウ素並びにホウ化物分布の測定技術開発を行った。ホウ素の中性子吸収に伴う即発ガンマ線を測定し、ホウ素量や二次元分布を測定した。また、n(B,$$alpha$$$$gamma$$)反応における478keV$$gamma$$線は、ホウ素の化合状態により、$$gamma$$線ピークの幅が変化することが知られている。このことを用い、特に溶融燃料棒周辺に存在することが予測されているZrBやFeBといったホウ化物の識別可能性について調査した。測定はJ-PARC/MLFのANNRI, NOBORU, RADENにて行った。これらの解析結果について報告する。

論文

Measurements of displacement cross section of tungsten under 389-MeV proton irradiation and thermal damage recovery

岩元 洋介; 吉田 誠*; 松田 洋樹; 明午 伸一郎; 佐藤 大樹; 八島 浩*; 薮内 敦*; 嶋 達志*

Materials Science Forum, 1024, p.95 - 101, 2021/03

核破砕中性子源,加速器駆動システム等における材料の照射損傷の基礎研究、マクロな材料特性研究、機器設計等をまとめた書籍の中で、われわれが主導してきた照射損傷量の指標である原子あたりのはじき出し数(DPA)に関する最新の研究を提示する。本研究では、タングステンのDPAの計算値を検証するため、ギフォード・マクマフォン冷凍機を用いてタングステン線を冷却し、389MeVの陽子照射による、極低温(10K)下の照射欠陥に伴う電気抵抗増加の測定値からはじき出し断面積を導出した。はじき出し断面積の実験値と計算値を比較した結果、これまでの発表者らが銅を用いた実験による検証結果と同様に、従来の照射損傷モデルによる計算値に比べて、最新の非熱的な欠陥再結合補正を考慮した計算値が実験値を良く再現することを明らかにした。また、アニールに伴う照射後の欠陥回復の測定により、60Kでは約20%の欠陥が回復し、原子炉の中性子照射環境と同様の結果となる他、銅の測定結果と比べた場合、タングステンにおける欠陥の回復量が少ないこと等を示した。

論文

High-spin states in $$^{35}$$S

郷 慎太郎*; 井手口 栄治*; 横山 輪*; 青井 考*; Azaiez, F.*; 古高 和禎; 初川 雄一; 木村 敦; 木佐森 慶一*; 小林 幹*; et al.

Physical Review C, 103(3), p.034327_1 - 034327_8, 2021/03

 被引用回数:2 パーセンタイル:62(Physics, Nuclear)

Excited states in $$^{35}$$S were investigated by in-beam $$gamma$$-ray spectroscopy using the $$^{26}$$Mg($$^{18}$$O, 2$$alpha$$1$$n$$) fusion-evaporation reaction. The de-exciting $$gamma$$-rays were measured with germanium detector arrays along with the measurement of evaporated charged particles in a $$4pi$$ segmented Si detector array. The level scheme was extended up to 12470 keV. The obtained level structure is compared with the large-scale shell-model calculations. The possibility of isoscalar-pair excited states is discussed for $$J=(17/2)$$ states with comparison between the experimental and theoretical results.

論文

Discovery of a new low energy neutron resonance of $$^{89}$$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:0 パーセンタイル:0.02(Physics, Nuclear)

A new neutron resonance of $$^{89}$$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 $$gamma$$-ray analysis. Neutron capture $$gamma$$-rays from $$^{89}$$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.

論文

Analytical method for the determination of $$^{211}$$At using an $$alpha$$-scintillation-camera system and thin-layer chromatography

瀬川 麻里子; 西中 一朗*; 藤 暢輔; 前田 亮

Journal of Radioanalytical and Nuclear Chemistry, 326(1), p.773 - 778, 2020/10

 被引用回数:1 パーセンタイル:20.43(Chemistry, Analytical)

$$^{211}$$At is a candidate nuclide for alpha-targeted therapy. In order to use $$^{211}$$At as a pharmaceutical, the radioactivity and chemical forms of generated $$^{211}$$At are the most fundamental specifications that need to be analyzed prior to its medical use. However, previous methods of separately measuring the radioactivity and chemical forms are not adaptable to the medical use of $$^{211}$$At because they cause a severe loss of $$^{211}$$At and do not analyze all the chemical forms of $$^{211}$$At. Therefore, a new analytical method for both the radioactivity and chemical forms of generated $$^{211}$$At is urgently needed. Accordingly, in this study, we developed an experimental system optimized to simultaneously analyze both the radioactivity and chemical forms of a $$^{211}$$At solution to significantly shorten the analysis time; we experimentally verified the accuracy and capabilities of this system at the Japan Atomic Energy Agency. The experiments confirmed that the present system could analyze the radioactivity and all the chemical forms of $$^{211}$$At with an uncertainty of approximately 5% in the region higher than 150 Bq and that it was 200 times more sensitive than the conventional method using an imaging technique with an X-ray imaging plate. As a result, a new method for analyzing the radioactivity and chemical forms of $$^{211}$$At was successfully established and this method will meet the demands for alpha-targeted therapy using $$^{211}$$At. This method will contribute to promoting the stable supply of the medical use of $$^{211}$$At in the near future.

論文

Study of shields against D-T neutrons for Prompt Gamma-ray Analysis apparatus in Active-N

古高 和禎; 藤 暢輔

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.297 - 304, 2020/10

No established method exists to non-destructively measure the amount of highly radioactive nuclear fuel materials such as spent fuels, and it is one of the urgent issues in nuclear material accountancy. Therefore, JAEA has started a research on development of innovative non-destructive analysis (NDA) system for Special Nuclear Materials and Minor Actinides, in cooperation with EC-JRC. The aim of the project is to establish an NDA method which can be applied to highly radioactive nuclear materials and develop a demonstration system, named "Active-N", by utilizing an intense D-T neutron source and by combining the following mutually complemental active-neutron NDA methods: DDA, N RTAs, and PGA (Prompt Gamma-ray Analysis). The PGA measurements play a crucial role in the system, because it can detect/quantify neutron poison elements which disturb DDA measurements, as well as explosives and chemical warfare agents, by utilizing a high-energy resolution Germanium detector. To make an NDA system to be efficient one, an intense neutron generator has to be employed. On the other hand, exposure of a Ge detector to an immense amount of fast neutron makes the detector severely damaged and inoperative. Therefore, in order for the system to be efficient, it is essential to develop effective shield of the PGA system against fast neutrons. In this work, by performing particle transport calculation using Monte Carlo method, we have investigated effective shielding methods for the PGA measurement system in the Active-N system, against fast neutrons from the D-T neutron source. Materials and their configurations which effectively reduce fast-neutron doses and at the same time emit no interfering gamma rays, were examined. Through the calculation, a shield which reduces fast neutron dose sufficiently have been developed. This research was implemented under the subsidiary for nuclear security promotion of MEXT.

論文

Study of the Li($$d,xn$$) reaction for the development of accelerator-based neutron sources

渡辺 幸信*; 定松 大樹*; 荒木 祥平*; 中野 敬太*; 川瀬 頌一郎*; 金 政浩*; 岩元 洋介; 佐藤 大樹; 萩原 雅之*; 八島 浩*; et al.

EPJ Web of Conferences, 239, p.20012_1 - 20012_4, 2020/09

 被引用回数:1 パーセンタイル:77.28

重陽子ビームによる加速器中性子源は、核分裂生成物の核変換、核融合炉材料試験等の応用分野での利用が検討されている。そこで、このような加速器や中性子源の設計に有益なデータとして、大阪大学核物理研究センターにおいて、200MeV重陽子入射核反応によるリチウムの中性子生成二重微分断面積(DDX)を測定した。実験では液体有機シンチレータEJ301を用いた飛行時間法を適用し、前方0度から25度の範囲で中性子断面積データを取得した。広範なエネルギー範囲のデータを取得するため、直径及び厚さが5.08cmと12.7cmの大きさの異なる2台のシンチレータを標的から7mと20mの地点にそれぞれ設置した。ここで、中性子の検出効率はSCINFUL-QMDコードを用いて導出した。本発表では、実験値と重陽子入射断面積計算コードDEURACS及び粒子・重イオン輸送計算コードPHITSによる計算値との比較について述べる。また、25, 40及び100MeV重陽子入射による実験値を用いて、DDXの入射エネルギー依存性について議論する。

417 件中 1件目~20件目を表示