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Development of active non-destructive analysis technologies for nuclear nonproliferation and security of JAEA

小泉 光生

Proceedings of 41st ESARDA Annual Meeting (Internet), p.260 - 267, 2019/05

The Japan atomic energy agency (JAEA) is developing active non-destructive analysis (NDA) technologies for nuclear nonproliferation and security under the support of the subsidiary of for "promotion of strengthening nuclear security or the like" of the Japanese government MEXT. One of the programs is "development of active neutron NDA techniques", in which four techniques are developed: i.e., Differential Die Away Analysis (DDA), Delayed Gamma-ray Analysis (DGA), Neutron Resonance Transmission Analysis (NRTA), and Prompt Gamma-ray Analysis (PGA). These techniques are used to complement each other. They would be useful for nuclear material accountancy, applicable to both low- and high-level radioactive nuclear materials (NMs), and for nuclear security purposes such as detection of NM and explosive materials. Another program is development of nuclear resonance fluorescence (NRF) technique for detection of NM hidden in a shield. This technique utilizes quasi monochromatic gamma-rays produced by laser Compton scattering (LCS) to irradiate a suspicious sample and observe NRF gamma-rays from that. Demonstration experiment of this technique will be performed soon. In this paper, the development projects are overviewed.


Potential for remote controllable systematization of the method of testing reinforced concrete using guided-wave on rebar

古澤 彰憲; 西村 昭彦; 竹仲 佑介; 村松 壽晴

Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet), 4 Pages, 2019/05



Application of nuclear data to the decommissioning of the Fukushima Daiichi Nuclear Power Station

奥村 啓介; Riyana, E. S.

JAEA-Conf 2018-001, p.63 - 68, 2018/12



Recent studies for structural integrity evaluation and defect inspection of J-PARC spallation neutron source target vessel

涌井 隆; 若井 栄一; 直江 崇; 新宅 洋平*; Li, T.*; 村上 一也*; 鹿又 研一*; 粉川 広行; 羽賀 勝洋; 高田 弘; et al.

Journal of Nuclear Materials, 506, p.3 - 11, 2018/08

 被引用回数:1 パーセンタイル:17.98(Materials Science, Multidisciplinary)



Neutron resonance transmission analysis for measurement of nuclear materials in nuclear fuel

土屋 晴文; 北谷 文人; 藤 暢輔; Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*

Proceedings of INMM 59th Annual Meeting (Internet), 6 Pages, 2018/07

In fields of nuclear safeguards and nuclear security, non-destructive assay (NDA) techniques are needed in order to quantify special nuclear materials (SNMs) in nuclear fuels. Among those techniques, active NDA ones would be preferable to passive ones. One candidate of active NDA techniques is neutron resonance transmission analysis (NRTA). In fact, experiments done at GELINA have shown that NRTA has high potential enough to quantify SNMs in complex materials. Currently, such a NRTA system requires a large electron accelerator facility to generate intense neutron sources. In other words, it is very difficult to perform NRTA at various facilities that need to measure SNMs. Thus, downsizing a NRTA system would be one solution of its difficulty. In order to realize a compact NRTA system, we develop a prototype with a D-T neutron generator that has a pulse width of 10 $$mu$$s. For this aim, numerical calculations to optimize the compact NRTA system were done. In addition, NRTA measurements with simulated fuel pins were made at neutron time-of-flight facilities such as GELINA. In this presentation, we present results of the numerical calculations and the experimental results. On the basis of those results we discuss a future prospect of a compact NRTA system that would be applicable to SNM quantification. This research was implemented under the subsidiary for nuclear security promotion of MEXT.


Development of delayed gamma-ray spectroscopy for nuclear material analysis

Rodriguez, D.; Rossi, F.; 高橋 時音; 瀬谷 道夫; 小泉 光生; Crochemore, J. M.*; Varasano, G.*; Bogucarska, T.*; Abbas, K.*; Pedersen, B.*

Proceedings of INMM 59th Annual Meeting (Internet), 7 Pages, 2018/07

DGS has great potential for HRNM, since it determines fissile nuclide compositions by correlating the observed DG spectrum to the unique FY of the individual nuclides. Experiments were performed with LRNM using both PUNITA and a JAEA designed Cf-shuffler tested in PERLA. The data was analyzed using an inverse MC method that both determines DG peak intensity correlations and provides an evaluation of the uncertainty of the measurements. The results were used to verify DG signatures for varying fissile compositions, total fissile content, and DGS interrogation timing patterns. Future development will focus on measuring HRNM and designing a compact system by evaluating different neutron sources, moderating materials, and detection capabilities. This presentation summarizes the JAEA/JRC DGS program to date and the future direction of this collaborative work performed using the MEXT subsidy for the promotion of strengthening nuclear security.


Study of the neutron multiplication effect in an active neutron method

米田 政夫; 大図 章; 森 貴正; 中塚 嘉明; 前田 亮; 呉田 昌俊; 藤 暢輔

Journal of Nuclear Science and Technology, 54(11), p.1233 - 1239, 2017/11

 被引用回数:5 パーセンタイル:58.67(Nuclear Science & Technology)



Ultrasonic guided wave approach for inspecting concave surface of the laser butt-welded pipe

古澤 彰憲; 西村 昭彦; 武部 俊彦*; 中村 将輝*; 竹仲 佑介*; 西條 慎吾*; 中本 裕之*

E-Journal of Advanced Maintenance (Internet), 9(2), p.44 - 51, 2017/08



A Proposal of secure non-destructive detection system of nuclear materials in heavily shielded objects and interior investigation system

瀬谷 道夫; 羽島 良一*; 呉田 昌俊

Proceedings of INMM 58th Annual Meeting (Internet), 10 Pages, 2017/07



Application of probability generating function to the essentials of nondestructive nuclear materials assay system using neutron correlation

細馬 隆

JAEA-Research 2016-019, 53 Pages, 2017/01


核物質非破壊測定システムの基礎への確率母関数の適用について研究を行った。最初に、高次の中性子相関を七重相関まで代数的に導出し、その基本的な性格を調べた。高次の中性子相関は、漏れ増倍率の増大に応じて急速に増大し、検出器の効率や設定によるが漏れ増倍率が1.3を超えると、より低次の中性子相関と交わり追い越してゆくことを見出した。続いて、高速中性子と熱中性子が共存する系において、高速中性子による核分裂数と二重相関計数率及び熱中性子による核分裂数と二重相関計数率を、代数的に導出した。従来の測定法と、differential die-away self-interrogation法によって得られるRossi-alpha結合分布と各エリアの面積比を用いれば、高速中性子と熱中性子それぞれの単位時間あたりの誘導核分裂数、ソース中性子1個あたりそれぞれの誘導核分裂数(1未満)及びそれぞれの二重相関計数率を、推定可能であることを見出した。


Evaluation of annealing and double ion beam irradiation by a laser-induced and laser-detected surface acoustic wave diagnostic system

北澤 真一*; 若井 栄一; 青砥 紀身

Radiation Physics and Chemistry, 127, p.264 - 268, 2016/10

 被引用回数:2 パーセンタイル:25.63(Chemistry, Physical)




直井 洋介; 小田 哲三; 富川 裕文

日本原子力学会誌ATOMO$$Sigma$$, 58(9), p.536 - 541, 2016/09




荻原 徳男; 引地 裕輔; 神谷 潤一郎; 金正 倫計

Journal of the Vacuum Society of Japan, 59(4), p.79 - 82, 2016/04

In order to demonstrate the function of the gas sheet for measuring the 2 dimensional profiles of the accelerated beams, the following experiments were carried out: (1) The gas sheet with a thickness of 1.5 mm and the density of 2$$times$$10$$^{-4}$$ Pa was generated by the combination of the deep slit and the thin slit. Here, the gas sheet was produced by the deep slit, and the shape of the sheet was improved by the thin slit. (2) For the electron beam of 30 keV with a diameter greater than 0.35 mm, the position and the two-dimensional profiles were well measured using the gas sheet.


The States of the art of the nondestructive assay of spent nuclear fuel assemblies; A Critical review of the Spent Fuel NDA Project of the U.S. Department of Energy's Next Generation Safeguards Initiative

Bolind, A. M.*; 瀬谷 道夫

JAEA-Review 2015-027, 233 Pages, 2015/12




高温工学試験研究炉(HTTR)の内部構造を可視化する; ミューオンを利用した非接触・非破壊検査技術の提案

高松 邦吉

放計協ニュース, (56), p.2 - 4, 2015/10

特願 2010-166333   開放特許情報データベース   公報

福島第一原子力発電所の事故前、宇宙線ミューオンを使って原子番号の違いを検出できないか検討した結果、散乱法を用いた宇宙線ミューオンの可視化技術は、黒鉛ブロック, 原子炉圧力容器, ウラン(燃料体), 空気を識別することができた。また、福島第一原子力発電所の事故後、燃料デブリの状況を把握するため、透過法を用いた宇宙線ミューオンの可視化技術を提案した結果、原子力機構のHTTRの原子炉圧力容器(RPV)および原子炉格納容器(CV)の外側から、炉心および炉内構造物を可視化することができた。


中性子多重相関計数法の数理的基礎; ウラン・プルトニウム混合二酸化物の例

細馬 隆

JAEA-Research 2015-009, 162 Pages, 2015/08


プルトニウム転換技術開発施設では、米国エネルギー省の支援を受けて中性子同時計数法による計量装置の開発・設置・改良を行い、20年にわたり計量管理と保障措置対応に用いてきた。中性子計数による測定の対象は今後、従来とは異なる自発核分裂性核種を含む高質量のウラン・プルトニウム混合二酸化物に拡がると思われる。そこで、中性子多重相関計数法の数理的基礎について現場での経験を含めて再考するとともに、次の点について基礎を拡充した; (a)確率母関数を用いた七重相関までの多重相関分布式の代数的導出; (b)モンテカルロ法に代えて試料内部の任意の点から表面の任意の点までの平均距離とこの間での誘導核分裂反応の確率を用いた漏れ増倍率の評価; (c)Poisson過程が持つ2つの異なる時間軸と同時計数の仕組みの関連付け、結果として確率過程に由来するほぼ同時中性子の導出と評価。分布式については「組合せ」に基づく新しい表現を併記し、実際に取り扱ったウラン・プルトニウム混合二酸化物をスペクトルや平均自由行程の例とした。


Technique of neutron resonance transmission analysis for active neutron NDA

土屋 晴文; 小泉 光生; 北谷 文人; 呉田 昌俊; 原田 秀郎; 瀬谷 道夫; Heyse, J.*; Kopecky, S.*; Mondelaers, W.*; Paradela, C.*; et al.

Proceedings of 37th ESARDA Annual Meeting (Internet), p.846 - 851, 2015/08



ミューオンを利用して高温工学試験研究炉(HTTR)の内部構造を可視化する; 非接触・非破壊で原子炉の内部構造を検査する

高松 邦吉

日本原子力学会誌ATOMO$$Sigma$$, 57(6), p.389 - 393, 2015/06

特願 2010-166333   開放特許情報データベース   公報



Cosmic-ray muon radiography for reactor core observation

高松 邦吉; 竹上 弘彰; 伊藤 主税; 鈴木 敬一*; 大沼 寛*; 日野 竜太郎; 奥村 忠彦*

Annals of Nuclear Energy, 78, p.166 - 175, 2015/04

 被引用回数:7 パーセンタイル:60.95(Nuclear Science & Technology)



Introduction to development of advanced safeguards and security NDA technologies by JAEA-ISCN

瀬谷 道夫; 呉田 昌俊; 曽山 和彦; 中村 仁宣; 原田 秀郎; 羽島 良一

Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07


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