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伊藤 孝; 門野 良典*
Journal of the Physical Society of Japan, 93(4), p.044602_1 - 044602_7, 2024/04
We propose a model to describe the fluctuations in the internal magnetic field due to ion dynamics observed in muon spin relaxation (
SR) by an Edwards-Anderson-type autocorrelation function that separates the quasi-static and dynamic components of the correlation by the parameter 
(where 
). Our Monte Carlo simulations for this model showed that the time evolution of muon spin polarization deviates significantly from the Kubo-Toyabe function. To further validate the model, the results of simulations were compared with the SR spectra observed in a hybrid organic-inorganic perovskite FAPbI
[with FA referring to HC(NH
)], where local field fluctuations associated with the rotational motion of FA molecules and quasi-static fields from the PbI lattice are presumed to coexist. The least-squares curve fitting showed reasonable agreement with the model with 
, and the fluctuation frequency of the dynamical component was obtained. This result opens the door to the possibility of experimentally distinguishing fluctuations due to the dynamics of ions around muons from those due to the self-diffusion of muons. On the other hand, it suggests the need to carefully consider the spin relaxation function when applying SR to the issue of ion dynamics.
涌井 隆; 高岸 洋一*; 二川 正敏
Materials, 16(17), p.5830_1 - 5830_16, 2023/09
被引用回数：0 パーセンタイル：0(Chemistry, Physical)水銀ターゲット容器は、陽子ビームの入射に伴い、キャビテーション損傷を受けるため、キャビテーションバブルの位置や衝撃圧力分布の不確実さを考慮して、モンテカルロ・シミュレーションを用いたキャビテーション損傷を予測する手法を提案した。本手法では、個々のキャビテーション気泡の崩壊に起因する衝撃圧力の分布はガウス分布とし、衝撃圧力の最大値の確率密度分布は3種類の分布: デルタ関数、ガウス分布、ワイブル分布と仮定した。衝撃圧力の分布を記述する方程式の2つのパラメータについて、実験から得られたキャビテーション損傷の分布とシミュレーションから得られた累積塑性ひずみの分布を比較し、ベイズ最適化を使用して推定することができた。また、ワイブル分布を用いて得られた結果が、他の結果に比べて、実際のキャビテーションエロージョン現象を再現することが分かった。
Rodriguez, D.; Rossi, F.
Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 9 Pages, 2023/05
Under the MEXT subsidy for the improvement of nuclear security related activities, we will present on the current and future progress of the delayed gamma-ray spectroscopic analysis development. We highlight a paper soon to be released and the plan for finalizing the project goal.
久保 光太郎; Jang, S.*; 高田 孝*; 山口 彰*
Journal of Nuclear Science and Technology, 60(4), p.359 - 373, 2023/04
被引用回数：5 パーセンタイル：78.52(Nuclear Science & Technology)確率論的リスク評価(PRA)は、原子力発電所の安全性を向上させるための重要なアプローチである。しかし、この手法では、複合ハザードのモデル化は困難である。地震に起因した溢水シナリオでは、地震による炉心損傷、溢水による炉心損傷、地震と溢水が組み合わさった炉心損傷といった複数の炉心損傷シーケンスを含んでいる。溢水に係るフラジリティは、溢水がタンクなどの水源から区画に伝播するため、時間依存性を有している。そのため、現実的なリスク評価及び定量化を行うためには、動的リスク評価を用いる必要がある。本研究では、地震,溢水,熱水力シミュレーションを連成させ、複数ハザード間の依存関係を明示的に考慮し、地震起因溢水のリスク評価を行った。特に、福島第一原子力発電所事故を踏まえた安全性向上対策に注目し、システムの耐力に関する感度解析と可搬型ポンプを用いた蒸気発生器代替注水の効果を評価した。我々は、シミュレーションに基づく動的PRA手法の複合ハザード起因のリスクの評価への使用を実証した。
Omer, M.; 静間 俊行*; 羽島 良一*; 小泉 光生
第43回日本核物質管理学会年次大会会議論文集(インターネット), 3 Pages, 2022/11
Gamma-rays originated from laser Compton scattering (LCS) are convenient photon sources for nondestructive interrogation of nuclear materials. LCS can be used with nuclear resonance fluorescence (NRF) and X-ray fluorescence (XRF), the two of which are considered photon-based active interrogation techniques. However, an accurate estimation of the incident LCS 
-ray flux is crucial. The -ray flux is customarily measured using high purity germanium (HPGe) detectors, usually calibrated using standard point-like radioactive -ray sources. These standard sources are entirely different from LCS beams in terms of detection geometry. Therefore, the calibration process must be corrected to meet the LCS beam conditions. Here, we demonstrate how to implement the required corrections and provide experimental validation of these corrections.
Omer, M.; 静間 俊行*; 羽島 良一*; 小泉 光生
Radiation Physics and Chemistry, 198, p.110241_1 - 110241_7, 2022/09
被引用回数：2 パーセンタイル：53.91(Chemistry, Physical)In beam geometries where a directed -ray beam hits the surface of a coaxial high purity germanium detector (HPGe), the detector efficiency is sensitive to the position where -rays initially hit the detector surface because the structure of the detector is nonuniform. This may cause inaccuracy of the detector efficiency when measured using standard sources that are point-like sources emitting -rays isotropically. Obtaining a precise estimation of the full energy peak efficiency of the coaxial HPGe detector in the beam geometry for on-axis and off-axis measurements requires a Monte Carlo simulation. We performed a Monte Carlo simulation that calculates the detector efficiency in the beam geometry. The effects of the off-axis distance and -ray beam size on the efficiency are quantitatively analyzed. We found that the intrinsic efficiency in the beam geometry is maximized when the beam hits the detector at specific off-axis distances. Our Monte Carlo calculations have been supported by a nuclear resonance fluorescence experiment using laser Compton scattering -ray beam.
古田 琢哉
医学物理, 41(4), P. 194, 2021/12
粒子・重イオン輸送計算コードPHITSは、近年における放射線の医学利用の高まりを受けて医学分野での利用例が増大しており、当該分野で有効な計算機能も開発されてきた。このような研究に関係する成果を、2021年にRadiological Physics and Technology誌で発表した「PHITSの医学物理計算への応用」と題するレビュー論文にまとめた。その後、日本医学物理学会の編集委員会より、この論文の内容を国内の関係者へ周知する紹介記事の投稿依頼があった。そこで、レビュー論文で報告したPHITSを利用した医学物理分野での応用例や有益なPHITSの機能、そしてユーザー間の情報交換の目的のために解説したPHITSフォーラムの情報等を日本医学物理学会誌で紹介する。
古田 琢哉; 佐藤 達彦
Radiological Physics and Technology, 14(3), p.215 - 225, 2021/09
PHITSユーザー数は、集計を開始した2010年以降に順調な増加傾向を示している。その中で、近年は医学物理分野における新規ユーザー数の増加が顕著となっている。そのため、PHITSを利用した数多くの研究が発表されており、その内容も放射線治療応用、施設の遮蔽計算、放射線生物学応用、医療機器研究開発等、多岐に渡っている。本稿では、これら応用研究の具体例を示しつつレビューを行うとともに、医学物理応用研究で有益なPHITSの機能を紹介する。
Cs and 
Cs radioactivity measurementsMalins, A.; 今村 直広*; 新里 忠史; 高橋 純子*; Kim, M.; 佐久間 一幸; 篠宮 佳樹*; 三浦 覚*; 町田 昌彦
Journal of Environmental Radioactivity, 226, p.106456_1 - 106456_12, 2021/01
被引用回数：6 パーセンタイル：35.21(Environmental Sciences)Understanding the relationship between the distribution of radioactive 
Cs and 
Cs in forests and ambient dose equivalent rates (
*(10)) in the air is important for researching forests in eastern Japan affected by the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident. This study used a large number of measurements from forest samples, including Cs and Cs radioactivity concentrations, densities and moisture contents, to perform Monte Carlo radiation transport simulations for *(10) between 2011 and 2017. Calculated *(10) at 0.1 and 1 m above the ground had mean residual errors of 19% and 16%, respectively, from measurements taken with handheld NaI(Tl) scintillator survey meters. Setting aside the contributions from natural background radiation, Cs and Cs in the organic layer and the top 5 cm of forest soil generally made the largest contributions to calculated *(10). The contributions from Cs and Cs in the forest canopy were calculated to be largest in the first two years following the accident. Uncertainties were evaluated in the simulation results due to the measurement uncertainties in the model inputs by assuming Gaussian measurement errors. The mean uncertainty (relative standard deviation) of the simulated *(10) at 1 m height was 11%. The main contributors to the total uncertainty in the simulation results were the accuracies to which the Cs and Cs radioactivities of the organic layer and top 5 cm of soil, and the vertical distribution of Cs and Cs within the 5 cm soil layers, were known. Radioactive cesium located in the top 5 cm of soil was the main contributor to *(10) at 1 m by 2016 or 2017 in the calculation results for all sites.
Malins, A.; 越智 康太郎; 町田 昌彦; 眞田 幸尚
Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.147 - 154, 2020/10
Compton-to-peak analysis is a method for selecting suitable coefficients to convert count rates measured with in situ gamma ray spectrometry to radioactivity concentrations of Cs & Cs in the environment. The Compton-to-peak method is based on the count rate ratio of the spectral regions containing Compton scattered gamma rays to that with the primary Cs & Cs photopeaks. This is known as the Compton-to-peak ratio (RCP). RCP changes as a function of the vertical distribution of Cs & Cs within the ground. Inferring this distribution enables the selection of appropriate count rate to activity concentration conversion coefficients. In this study, the PHITS Monte Carlo radiation transport code was used to simulate the dependency of RCP on different vertical distributions of Cs & Cs within the ground. A model was created of a LaBr(Ce) detector used in drone helicopter aerial surveys in Fukushima Prefecture. The model was verified by comparing simulated gamma ray spectra to measurements from test sources. Simulations were performed for the infinite half-space geometry to calculate the dependency of RCP on the mass depth distribution (exponential or uniform) of Cs & Cs within the ground, and on the altitude of the detector above the ground. The calculations suggest that the sensitivity of the Compton-to-peak method is greatest for the initial period following nuclear fallout when Cs & Cs are located close to the ground surface, and for aerial surveys conducted at low altitudes. This is because the relative differences calculated between RCP with respect to changes in the mass depth distribution were largest for these two cases. Data on the measurement height above and on the Cs & Cs activity ratio is necessary for applying the Compton-to-peak method to determine the distribution and radioactivity concentration of Cs & Cs in the ground.
Riyana, E. S.; 奥村 啓介; 寺島 顕一; 松村 太伊知; 坂本 雅洋
Mechanical Engineering Journal (Internet), 7(3), p.19-00543_1 - 19-00543_8, 2020/06
Prediction of the fuel debris location and distribution inside the primary containment vessel (PCV) of the Fukushima Daiichi Nuclear Power Plant is important to decide further decommissioning step and strategy. The radiation measurements in the past internal investigations have not yet provided enough information to predict fuel debris location and its distribution inside PCV. To support further measurement efforts, we simulate the detector response inside the PCV. The calculation result could provide a base on deciding suitable detector systems to assist the efforts on searching, localizing and defining distributions of the fuel debris.
Malins, A.; 町田 昌彦; Vu, TheDang; 相澤 一也; 石田 武和*
Nuclear Instruments and Methods in Physics Research A, 953, p.163130_1 - 163130_7, 2020/02
被引用回数：6 パーセンタイル：60.71(Instruments & Instrumentation)Radiation transport simulations were used to analyse neutron imaging with the current-biased kinetic inductance detector (CB-KID). The PHITS Monte Carlo code was applied for simulating neutron, 
He, 
Li, photon and electron transport, 
B(n,
)Li reactions, and energy deposition by particles within CB-KID. Slight blurring in simulated CB-KID images originated He and Li ions spreading out in random directions from the B conversion layer in the detector prior to causing signals in the 
and 
superconducting Nb nanowire meander lines. 478 keV prompt gamma rays emitted by Li nuclei from neutron-B reactions had negligible contribution to the simulated CB-KID images. Simulated neutron images of B dot arrays indicate that sub 10 m resolution imaging should be feasible with the current CB-KID design. The effect of the geometrical structure of CB-KID on the intrinsic detection efficiency was calculated from the simulations. An analytical equation was then developed to approximate this contribution to the detection efficiency. Detection efficiencies calculated in this study are upper bounds for the reality as the effects of detector temperature, the bias current, signal processing and dead-time losses were not taken into account. The modelling strategies employed in this study could be used to evaluate modifications to the CB-KID design prior to actual fabrication and testing, conveying a time and cost saving.
-rays elastic scattering by Monte Carlo simulationOmer, M.; 羽島 良一*
New Journal of Physics (Internet), 21(11), p.113006_1 - 113006_10, 2019/11
被引用回数：5 パーセンタイル：42.69(Physics, Multidisciplinary)Nuclear resonance fluorescence (NRF) is a promising technique for nondestructive assay (NDA) of nuclear materials. Its strength is improved when polarized -ray beams are used as probes because the polarized -rays provide an asymmetry in the intensity of the scattered photons. Nonetheless, NRF interaction takes place with other interactions such as elastic scattering of -rays. These interactions are unavoidable background which may limit the sensitivity of the NRF technique. Therefore, estimating polarization effects of elastic scattering is a significant factor in assessing the NRF method. Here, we implement a new Monte Carlo simulation to account for polarization effects of the elastic scattering. The simulation is based on explicit expressions driven in the Stokes parameters formalism. The scattering amplitudes of Rayleigh, nuclear Thomson, and Delbr
ck scattering processes have been superimposed into a two-orthogonal set of complex amplitudes. This set is then exploited to construct the core of the simulation in a way such that the simulation could handle arbitrary polarization states of the incoming beam and correspondingly generate polarization states for the outgoing beam. This work was supported by the subsidiary for promotion of strengthening nuclear security or the like of the Ministry of Education, Culture, Sports, Science, and Technology (MEXT), Japan.
古田 琢哉; El Basha, D.*; Iyer, S. S. R.*; Correa Alfonso, C. M.*; Bolch, W. E.*
Journal of Radiological Protection, 39(3), p.825 - 837, 2019/09
被引用回数：2 パーセンタイル：21.58(Environmental Sciences)人の眼球には多様性があるにもかかわらず、これまでの眼球に対する線量計算シミュレーションでは、ほぼ全ての研究で標準的な一つのモデルが採用されてきた。そこで、本研究では新たに開発した大きさ及び変形が可能な数値眼球モデルを利用し、モンテカルロ放射線輸送計算コードPHITSを用いて、標準的な照射場(AP, PA, RLAT, ROT等)での電子線,光子線および中性子線による眼球内組織の線量を計算した。ここでは、5種類(標準,大型,小型,近視形状型および遠視形状型)の極端な眼球モデルの計算結果の比較に基づき、組織の吸収線量への眼球の大きさや変形が与える影響を解析した。電子線では線量の集中性が高く、吸収線量は眼球表面からの組織の深さに大きく依存して変化する。このため、眼球の大きさや変形に伴い、組織全体の深さ位置が変化することによる吸収線量への顕著な影響が見られた。これに対し、光子線や中性子線では電子線に比べて線量の集中性が弱いため、眼球の大きさや変形による影響が小さいことがわかった。
橋本 慎太郎; 佐藤 達彦
Journal of Nuclear Science and Technology, 56(4), p.345 - 354, 2019/04
被引用回数：5 パーセンタイル：48.99(Nuclear Science & Technology)モンテカルロ法に基づいた粒子輸送シミュレーションは、加速器施設の遮蔽計算等の様々な目的で利用されている。モンテカルロ法による計算結果の信頼性を定量的に評価するためには、試行回数によって決まる統計的不確かさに加えて、計算で使われる反応断面積や計算の入力情報となる遮蔽材の密度がもつ誤差の影響を系統的不確かさとして求める必要がある。本研究の評価方法は分散分析に基づいており、これを鉄やコンクリートを遮蔽材とする中性子の遮蔽計算の解析に適用し、統計的及び系統的不確かさの両方を評価可能であることを示した。その際、入力情報の値を誤差の範囲で変動させるランダム条件法の他、三条件(中央値,上限値及び下限値)のみ変動させる三条件法を提案した。ランダム条件法は計算体系に関わらず適切に系統的不確かさが評価できるものの長い計算時間を必要とするのに対し、入力情報の誤差の影響が複雑な場合を除いて、三条件法は計算時間を抑えてランダム条件法と同じ評価結果を与えることがわかった。さらに、試行回数を増加させた場合の収束状況を判断できる新しい基準値を示し、必要最小限の計算時間で収束した評価結果が得られることを明らかにした。
木名瀬 栄; Mohammadi, A.*; G
mez-Ros, J.-M.*
Computational Anatomical Animal Models; Methodological Developments and Research Applications, p.5_1 - 5_9, 2018/12
被引用回数：0 パーセンタイル：0.04(Anatomy & Morphology)There are limited investigations on the computational frog models and the organ dose evaluations for frogs in environmental protection. In this article, computational frog models and their applications are reviewed to share some perspectives of frog model development in the near future. The authors hope that 3D printing frog phantoms with adequate tissue substitutes should be developed for the validation of the dosimetric quantities by the Monte Carlo simulations.
Rossi, F.; Rodriguez, D.; 高橋 時音; 瀬谷 道夫; 小泉 光生
日本核物質管理学会第39回年次大会論文集(CD-ROM), 3 Pages, 2018/11
この発表では、再処理施設の溶解溶液等の高放射性核物質サンプルの核分裂性核種比の検認に適用される、遅発ガンマ線分光非破壊分析システムの減速体(反射体)のコンパクト性を追求する設計研究について報告する。我々は、最初に小型中性子源としてDT及びDD中性子源を使った場合の有利、不利を調べた。この結果、DD中性子源がコンパクトで実用的なNDAシステムが達成できることが示された。ここではMCNPシミュレーションにより実施した、DD中性子源を使う予備的な最適化設計を報告する。
El Basha, D.*; 古田 琢哉; Iyer, S. S. R.*; Bolch, W. E.*
Physics in Medicine & Biology, 63(10), p.105017_1 - 105017_13, 2018/05
被引用回数：10 パーセンタイル：51.74(Engineering, Biomedical)眼の水晶体に対する年間線量限度の推奨値の引き下げが国際放射線防護委員会より発表されて以降、眼の詳細構造に対する線量予測システムの構築に関心が高まっている。これを受けて線量評価に用いる詳細な数値眼球モデルがいくつか開発されたが、いずれのモデルも典型的な球形・通常サイズの正常視眼球モデルであった。そこで、サイズおよび形状の変更が可能で放射線被ばく及び眼疾患の放射線治療のシミュレーションに使用できる解析関数眼球モデルを開発した。この眼球モデルを利用したシミュレーションの一例として、前方照射条件での電子および光子の放射線輸送計算を実行し、入射エネルギーを変化させた場合の眼球内詳細構造に対する線量応答を調べた。前方照射条件のため、各構造の深さ位置が重要で、眼球サイズが大きい場合や近視のために眼球が扁長変形を持つ場合は、通常サイズの正視の場合に比べて各構造が深い位置にずれるため、エネルギー応答が少し高エネルギー側にシフトする傾向があることがわかった。
-rays at the ANNRI in the MLF of the J-PARC高田 秀佐*; 奥平 琢也*; 後藤 文也*; 広田 克也*; 木村 敦; 北口 雅暁*; 古賀 淳*; 中尾 太郎*; 酒井 健二; 清水 裕彦*; et al.
Journal of Instrumentation (Internet), 13(2), p.P02018_1 - P02018_21, 2018/02
被引用回数：6 パーセンタイル：31.02(Instruments & Instrumentation)In this study, the germanium detector assembly, installed at the Accurate Neutron Nuclear Reaction measurement Instruments (ANNRI) in the Material and Life Science Facility (MLF) operated by the Japan Proton Accelerator Research Complex (J-PARC), has been characterized for extension to the measurement of the angular distribution of individual -ray transitions from neutron-induced compound states. We have developed a Monte Carlo simulation code using the GEANT4 toolkit, which can reproduce the pulse-height spectra of -rays from radioactive sources and (n,) reactions. The simulation is applicable to the measurement of -rays in the energy region of 0.5-11.0 MeV.
Lerendegui-Marco, J.*; Cort
s-Giraldo, M. A.*; Guerrero, C.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他114名*
EPJ Web of Conferences, 146, p.03030_1 - 03030_4, 2017/09
被引用回数：0 パーセンタイル：0.08(Nuclear Science & Technology)Monte Carlo (MC) simulations are an essential tool to determine fundamental features of a neutron beam, such as the neutron flux or the ray background, that sometimes can not be measured or at least not in every position or energy range. Until recently, the most widely used MC codes in this field had been MCNPX and FLUKA. However, the Geant4 toolkit has also become a competitive code for the transport of neutrons after the development of the native Geant4 format for neutron data libraries, G4NDL. In this context, we present the Geant4 simulations of the neutron spallation target of the n TOF facility at CERN, done with version 10.1.1 of the toolkit. The first goal was the validation of the intra-nuclear cascade models implemented in the code using, as benchmark, the characteristics of the neutron beam measured at the first experimental area (EAR1), especially the neutron flux and energy distribution, and the time distribution of neutrons of equal kinetic energy, the so-called Resolution Function. The second goal was the development of a Monte Carlo tool aimed to provide useful calculations for both the analysis and planning of the upcoming measurements at the new experimental area (EAR2) of the facility.
