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Ba 
-ray calibration field for photon energy in the 300-400 keV range辻 智也; 吉富 寛; 古渡 意彦*; 佐藤 文信*; 谷村 嘉彦
Radiation Protection Dosimetry, 202(8), p.619 - 630, 2026/05
被引用回数：0 パーセンタイル：0.00(Environmental Sciences)A -ray calibration field using a sealed Ba source for photon energy in the 300 - 400 keV range was established at the Japan Atomic Energy Agency to evaluate radiation protection devices under low dose rate conditions. To suppress low-energy -ray components, a 2-mm lead filter was applied. The photon fluence spectrum was measured using a CdTe spectrometer and an unfolding method, yielding a spectrum with a mean energy of 321 keV. Reference air kerma rates were determined using ionization chambers calibrated in a 
Cs field, with energy correction factors applied. Spectrometry using a CeBr
scintillation spectrometer combined with the G(E) function method was employed to validate these corrections. Spectrum-averaged conversion coefficients were derived from the measured spectrum, indicating equivalence to the N-400 radiation quality. This field provided air kerma rates from 0.22 to 2.13 
Gy h
, suitable for testing devices used in environmental monitoring and nuclear emergency response.
辻 智也; 吉富 寛; 佐藤 文信*; 谷村 嘉彦
Radioisotopes, 75(S-01), p.S-004_1 - S-004_6, 2026/04
Radiation dosimeters must be well calibrated and tested according to international standards. In the ISO 4037:2019 standard series, requirements regarding photon calibration fields to be used are clearly specified. The X-ray narrow-spectrum series (N-series) calibration field is commonly used to test energy response of dosimeters. Thus, we established an N-series calibration field using a soft X-ray generator, YXLON MG165/4.5, at the Facility of Radiation Standards (FRS) of Japan Atomic Energy Agency (JAEA). The radiation quality of an X-ray calibration field is characterized by the following parameters: mean energy of a beam, resolution of X-ray spectral fluence, half-value layer (HVL) of Al or Cu filters with respect to air kerma and homogeneity coefficient. The established calibration fields were verified to ensure that these parameters were in accordance with the recommendations of the ISO 4037-1:2019 based on measurements.
佐藤 達彦; 塩田 大幸*; 久保 勇樹*; 片岡 龍峰*; 保田 浩志*; 三宅 晶子*; 石井 守*; 三好 由純*
Space Weather, 24(4), p.e2026SW004949_1 - e2026SW004949_13, 2026/04
被引用回数：0 パーセンタイル：0.00(Astronomy & Astrophysics)WASAVIES (WArning System for AVIation Exposure to Solar energetic particles) is a physics-based nowcasting system designed to support warning operations for aviation exposure to solar energetic particles (SEPs) by providing near-real-time global SEP dose-rate estimates. On 11 November 2025, ground level enhancement GLE77 occurred and successfully triggered the SEP mode of WASAVIES, demonstrating fully autonomous initiation of global SEP dose-rate nowcasts during an extreme space-weather event. We performed a post-event reanalysis using a patched version of the operational algorithm to mitigate these issues. Our analysis indicates that the estimated global maximum effective dose rate (including the galactic cosmic-ray contribution) briefly exceeded the ICAO Moderate advisory threshold at altitudes of 14 km and above, but the exceedance was short-lived and limited in magnitude and geographic extent. This finding confirms that GLE77 did not warrant major operational responses such as route or altitude changes. Overall, these results validate the operational potential of WASAVIES and identify key upgrades needed to ensure stable, reliable nowcasts for future extreme events.
Rahim, A.*; 佐藤 達彦; 福田 寛*; Beni, M. S.*; 渡部 浩司*
Biomedical Physics & Engineering Express (Internet), 12(1), p.015056_1 - 015056_13, 2026/01
Proton boron fusion therapy (PBFT) aims to enhance proton therapy through 
particles generated by the 
reaction. While early reports suggested large dose gains near the Bragg peak, later studies questioned its feasibility due to the low cross section and the need for unrealistically high boron concentrations. In this study, Monte Carlo microdosimetric analysis showed that protons dominate total dose delivery, with particles contributing only locally to high-LET deposition. The resulting RBE enhancement factors were negligible at 100-1000 ppm boron and modest (
) only at 10,000 ppm. These findings indicate that, under clinically realistic conditions, the therapeutic benefit of PBFT is minimal.
宮原 信哉*; 鯉江 竜輔*; 宇埜 正美*; 河口 宗道*; 佐藤 理花; 清野 裕
Nuclear Engineering and Design, 446(Part A), p.114523_1 - 114523_14, 2026/01
被引用回数：2 パーセンタイル：65.74(Nuclear Science & Technology)In a postulated accident of fuel pin failure of a sodium-cooled fast reactor, a fission product of cesium will be released from the failed pin as an aerosol such as cesium iodide and/or cesium oxide together with a fission product noble gas such as xenon and krypton. The xenon and krypton released with the cesium aerosols into the sodium coolant as bubbles have an influence on the removal of cesium aerosols by the sodium pool in a period of bubble rising to the sodium pool surface. Then, the cesium aerosols could transfer into the containment vessel as an initial inventory of a source term. To meet this phenomenon, the computer program AESOP (AErosol scrubbing in SOdium Pool) has been developed to deal with the expansion and the deformation of the bubble together with the aerosol absorption considering the effects of the particle size distribution and the agglomeration in aerosols. In this study, simulation experiments have been conducted using simulant particles under the condition of room temperature in water pool and nitrogen gas bubble systems and the experimental results were compared with the analysis results calculated under the same condition by the AESOP code. Furthermore, to examine the applicability of the AESOP code to the sodium pool system, the sensitivities of the physical parameters on decontamination factor (DF) of fission product aerosols such as the initial bubble diameter, the sodium pool depth and the temperature, the aerosol particle diameter and the density, the initial aerosol concentration in the bubble had been studied and the analysis results were discussed for the sensitivities of the parameter as same as DF of the aerosol.
辻 智也; 吉富 寛; 西野 翔; 佐藤 文信*; 谷村 嘉彦
Journal of Radiological Protection, 45(3), p.031519_1 - 031519_8, 2025/09
被引用回数：0 パーセンタイル：0.00(Environmental Sciences)In response to the new operational quantities proposed in ICRU Report 95, we calculated conversion coefficients for high monoenergetic photon calibration fields-specifically, the 
Am -ray calibration field and the fluorescence X-ray calibration field-both of which are listed in the annex of the ISO 4037 standard series. These coefficients were derived using measured photon spectral fluence. Additionally, correction factors for air density were determined for the low-energy fluorescence X-ray calibration field. Both the conversion coefficients and the air density correction factors were found to vary within the standard uncertainty specified by the ISO 4037 series.
辻 智也; 吉富 寛; 佐藤 文信*; 谷村 嘉彦
Radiation Protection Dosimetry, 201(9), p.648 - 662, 2025/06
被引用回数：3 パーセンタイル：65.74(Environmental Sciences)An irradiation environment for dosemeters calibration in the fluorescence X-ray field was set up at the Facility of Radiation Standards of the Japan Atomic Energy Agency (JAEA) by re-establishing the fluorescence X-ray calibration field that was established in 1989. The reference air kerma rates were determined using reference ionization chambers (ICs) calibrated using X-ray narrow-spectrum series calibration field of the national metrology standard (NMS) in Japan. Since no X-ray calibration field using fluorescence X-rays is available in Japan, the measurements were corrected by factors that accounts for differences in the fluorescence X-ray calibration field energy and the X-ray narrow-spectrum series calibration field energy. The conversion coefficients and correction factors for air densities for the fluorescence X-ray calibration field, including those unavailable in the ISO 4037 standard series, were derived from the measured X-ray fluence rate spectra.
井上 倫太郎*; 小田 隆; 中川 洋; 富永 大輝*; 池上 貴久*; 小沼 剛*; 岩瀬 裕希*; 川北 至信; 佐藤 衛*; 杉山 正明*
Biophysical Journal, 124(3), p.540 - 548, 2025/02
被引用回数：3 パーセンタイル：53.37(Biophysics)Intrinsically disordered proteins (IDPs) show structural changes stimulated by changes in external conditions. This study aims to reveal the temperature dependence of the structure and the dynamics of the intrinsically disordered region of the helicase-associated endonuclease for fork-structured DNA, one of the typical IDPs, using an integrative approach. Small-angle X-ray scattering (SAXS) and circular dichroism (CD) studies revealed that the radius of gyration and ellipticity at 222 nm remained constant up to 313-323 K, followed by a decline above this temperature range. NMR studies revealed the absence of a promotion of the -helix. As a result, SAXS, CD, and NMR data strongly suggest that these temperature-dependent structural changes were primarily due to a reduction in the content of the polyproline II (PPII) helix. Moreover, quasielastic neutron scattering studies revealed a slight change in the activation energy in a similar temperature range. Considering the concept of glass transition, it is posited that dynamical cooperativity between the PPII helix and water may play a significant role in these structural changes. The findings suggest that internal dynamics are crucial for regulating the structure of IDPs, highlighting the importance of considering dynamical cooperativity in future studies of protein behavior under varying temperature conditions.
佐藤 楓*; 相楽 洋*; Han, C. Y.*; 木村 祥紀; 田辺 鴻典*
第45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, 2024/11
我が国では、再処理工程において多様な形態で回収Puを取り扱うことから、それらの起源や履歴といった情報の特定に資する核鑑識シグネチャを明らかにすることが重要である。本研究では、核鑑識の重要パラメータの一つである燃料核種組成情報を活用して、多様な形態で存在する回収Puが生成された原子炉型(PWRs, BWRs, FRs)、燃料型、再処理工程における分離精製年代を推定するために、機械学習を用いた重要シグネチャ核種の検討を行った。
小川 達彦; 平田 悠歩; 松谷 悠佑; 甲斐 健師; 佐藤 達彦; 岩元 洋介; 橋本 慎太郎; 古田 琢哉; 安部 晋一郎; 松田 規宏; et al.
EPJ Nuclear Sciences & Technologies (Internet), 10, p.13_1 - 13_8, 2024/11
放射線挙動解析コードPHITSは、モンテカルロ法に基づいてほぼ全ての放射線の挙動を解析することができる放射線挙動解析計算コードである。その最新版であるPHITS version 3.34の、飛跡構造解析機能に焦点を置いて説明する。飛跡構造解析とは、荷電粒子が物質中を運動する挙動を計算する手法の一つで、個々の原子反応を識別することにより原子スケールでの追跡を可能にするものである。従来の飛跡構造解析モデルは生体を模擬する水だけにしか適用できず、遺伝子への放射線損傷を解析するツールとして使われてきた飛跡構造解析であるが、PHITSにおいてはPHITS-ETS、PHITS-ETS for Si、PHITS-KURBUC、ETSART、ITSARという飛跡構造解析モデルが補い合うことにより、生体の放射線影響だけでなく、半導体や材料物質など任意物質に対する適用が可能になっている。実際にこれらのモデルを使って、放射線によるDNA損傷予測、半導体のキャリア生成エネルギー計算、DPAの空間配置予測など、新しい解析研究も発表されており、飛跡構造解析を基礎とするボトムアップ型の放射線影響研究の推進に重要な役割を果たすことが期待できる。
秋葉 宙*; 大政 義典*; 古府 麻衣子*; Zhang, M.*; 佐藤 駿*; 山室 修*
Journal of the Physical Society of Japan, 93(9), p.091010_1 - 091010_6, 2024/09
被引用回数：2 パーセンタイル：18.32(Physics, Multidisciplinary)AGNES is a direct geometry chopper-type time-of-flight neutron spectrometer installed at the cold neutron guide (C3-1-1) of JRR-3 (Tokai, Japan). This instrument is well-suited for studies on low-energy excitations of powdered and amorphous samples, and quasi-elastic scattering with an energy resolution of 120 eV (standard mode) or 50 eV (high-resolution mode). During the long shutdown period of JRR-3 due to the Great East Japan Earthquake in 2011, AGNES was significantly improved through the installation of supermirror-coated neutron guide tubes and collimator, installation of a new-type top-loading cryo-furnace, and renewal of data acquisition electronics and software. As a result, the neutron intensity has increased by 7.7 times in the standard mode and by 3.2 times in the high-resolution mode. These enhancements facilitate experiments with small amounts of samples, and under special environments, which have previously been challenging.
森戸 誠*; 藤井 俊*; 吉村 洸貴*; 眞田 幸尚; 馬場 尚一郎*; 松永 浩志*; Mori, Takami*; 佐藤 憲一郎*; 田原 淳一郎*
Proceedings of 34th International Ocean and Polar Engineering Conference (ISOPE-2024), p.3754 - 3761, 2024/06
本研究では、海底地盤の放射線計測を行う無人探査機の制御手法として、スライディングモード制御とニューラルネットワークを組み合わせた手法を提案する。制御入力のベースとしてスライディングモード制御を用い、スライディングモード制御のパラメータの一つである
とその変化率が小さくなるようにニューラルネットワークコントローラを用いて補正入力を加える。本方式を用いた制御システムを製作した後、シミュレーション試験、海域試験を行い、本方式による調査が可能かどうかを評価した。
藁科 友朗*; 佐藤 朝子*; 比内 浩; Shaikhutdinov, N.*; Shagimardanova, E.*; 森 宙史*; 玉木 聡志*; 斎藤 元文*; 眞田 幸尚; 佐々木 祥人; et al.
Applied and Environmental Microbiology, 90(4), p.e02113-23_1 - e02113-23_23, 2024/04
被引用回数：2 パーセンタイル：20.55(Biotechnology & Applied Microbiology)A major incident occurred at the Fukushima Daiichi Nuclear Power Station following the tsunami triggered by the Tohoku-Pacific Ocean Earthquake in March 2011, whereby seawater entered the torus room in the basement of the reactor building. Here, we identify and analyze the bacterial communities in the torus room water and several environmental samples. Samples of the torus room water (1 
10
BqCs/L) were collected by the Tokyo Electric Power Company Holdings from two sampling points between 30 cm and 1 m from the bottom of the room (TW1) and the bottom layer (TW2). A structural analysis of the bacterial communities based on 16S rRNA amplicon sequencing revealed that the predominant bacterial genera in TW1 and TW2 were similar. TW1 primarily contained the genus Limnobacter, a thiosulfate-oxidizing bacterium. -Irradiation tests on Limnobacter thiooxidans, the most closely related phylogenetically found in TW1, indicated that its radiation resistance was similar to ordinary bacteria. TW2 predominantly contained the genus Brevirhabdus, a manganese- oxidizing bacterium. Although bacterial diversity in the torus room water was lower than seawater near Fukushima, 
70% of identified genera were associated with metal corrosion. Latent environment allocation - an analytical technique that estimates habitat distributions and co-detection analyses - revealed that the microbial communities in the torus room water originated from a distinct blend of natural marine microbial and artificial bacterial communities typical of biofilms, sludge, and wastewater. Understanding the specific bacteria linked to metal corrosion in damaged plants is important for advancing decommissioning efforts.
渡部 浩司*; 佐藤 達彦; Yu, K. N.*; Zivkovic, M.*; Krstic, D.*; Nikezic, D.*; Kim, K. M.*; 山谷 泰賀*; 河地 有木*; 田中 浩基*; et al.
Radiation Protection Dosimetry, 200(2), p.130 - 142, 2024/02
被引用回数：4 パーセンタイル：48.90(Environmental Sciences)DynamicMCは、人体ファントムが単色線源に照射されたときの3次元線量分布を簡単に計算可能なGUIソフトウェアである。従来は、米国産放射線挙動解析コードMCNPと接続して使うよう設計されていた。本研究では、DynamicMCをPHITSと接続して使うように改良し、いくつかの新機能を付加した。具体的な改良点は以下の通りである。(1)単色のみならず放射性同位元素の崩壊により生じる様々なエネルギースペクトルを持つ線源に対応可能とした、(2)臓器吸収線量を計算可能とした、(3)複数の条件に対する平均線量を計算可能とした、(4)遮蔽物の影響を考慮可能とした。本改良により、DynamicMCは放射線防護の研究や教育など様々な目的で利用可能となった。
佐藤 達彦; 岩元 洋介; 橋本 慎太郎; 小川 達彦; 古田 琢哉; 安部 晋一郎; 甲斐 健師; 松谷 悠佑; 松田 規宏; 平田 悠歩; et al.
Journal of Nuclear Science and Technology, 61(1), p.127 - 135, 2024/01
被引用回数：396 パーセンタイル：99.98(Nuclear Science & Technology)放射線挙動解析コードPHITSは、モンテカルロ法に基づいてほぼ全ての放射線の挙動を解析することができる。その最新版であるPHITS version 3.31を開発し公開した。最新版では、高エネルギー核データに対する親和性や飛跡構造解析アルゴリズムなどが改良されている。また、PHIG-3DやRT-PHITSなど、パッケージに組み込まれた外部ソフトウェアも充実している。本論文では、2017年にリリースされたPHITS3.02以降に導入された新しい機能について説明する。
池内 宏知; 佐々木 新治; 大西 貴士; 仲吉 彬; 荒井 陽一; 佐藤 拓未; 多木 寛; 関尾 佳弘; 山口 祐加子; 森下 一喜; et al.
JAEA-Data/Code 2023-005, 418 Pages, 2023/12
JAEA-Data-Code-2023-005-01.pdf:24.59MBJAEA-Data-Code-2023-005-02.pdf:32.18MB
東京電力ホールディングス(株)福島第一原子力発電所(1F)の廃炉作業を安全かつ着実に実施するためには、炉内で生成した燃料デブリの組成や物理的・化学的特性等の性状を把握し、燃料デブリの取り出しや収納・保管等の実際の廃炉作業を検討するプロジェクトに提供していく必要がある。この目的から、1F2号機の内部調査で取得された付着物や堆積物等の汚染物サンプルを用いて、サンプル中の成分の把握及び燃料由来のウランを含む微粒子(U含有粒子)の詳細観察を行った。本報告書は、サンプルの成分由来やU含有粒子の生成過程等の解析評価に供するため、2021年度に得られた分析結果として、FE-SEM/WDX、FE-SEM/EDX、TEM/STEM-EDXによる詳細観察画像や元素分析結果、放射線測定結果及びICP-MSによる元素分析結果をデータベースとしてまとめたものである。
states in the electronic structure of the intermediate-valence superconductor CeIr
藤森 伸一; 川崎 郁斗; 竹田 幸治; 山上 浩志; 雀部 矩正*; 佐藤 芳樹*; 清水 悠晴*; 仲村 愛*; Maruya, A.*; 本間 佳哉*; et al.
Electronic Structure (Internet), 5(4), p.045009_1 - 045009_7, 2023/11
The electronic structure of the 
-based superconductor 
was studied by photoelectron spectroscopy. The energy distribution of the 
state was revealed by the 
resonant photoelectron spectroscopy. The state was mostly distributed in the vicinity of the Fermi energy, suggesting the itinerant character of the state. The contribution of the state to the density of states (DOS) at the Fermi energy was estimated to be nearly half of that of the
states, implying that the state has aconsiderable contribution to the DOS at the Fermi energy. The 
core-level and X-ray absorption spectra were analyzed based on a single-impurity Anderson model. The number of the state in the ground state was estimated to be 0.8-0.9, which is much larger than the values obtained in the previous studies (i.e., 0-0.4).
間所 寛; 山下 拓哉; Gaus-Liu, X.*; Cron, T.*; Fluhrer, B.*; 佐藤 一憲; 溝上 伸也*
Nuclear Technology, 209(2), p.144 - 168, 2023/02
被引用回数：3 パーセンタイル：29.23(Nuclear Science & Technology)Since the reactor pressure vessel (RPV) lower head failure determines the subsequent ex-vessel accident progression, it is a key issue to understand the accident progression of Fukushima Daiichi Nuclear Power Station (1F). The RPV failure is largely affected by thermal loads on the vessel wall and thus it is inevitable to understand thermal behavior of molten metallic pool with co- existence of solid oxide fuel debris. In the past decades, numerous experiments have been conducted to investigate a homogeneous molten pool behavior. Few experiments, however, addresses the melting and heat transfer process of debris bed consisted of materials with different melting temperatures. LIVE-J2 experiment aimed to provide the experimental data on a solid-liquid mixture pool in a simulated RPV lower head under various conditions. The extensive measurements of the melt temperature indicate the heat transfer regimes in a solid-liquid mixture pool. The test results showed that the conductive heat transfer was dominant during the steady state along the vessel wall boundary and that convective heat transfer takes place inside the mixture pool. Besides the experimental performance, the test case was numerically simulated by using ANSYS Fluent. The simulation results generally agree with the measured experimental data. The flow regime and transient melt evolution were able to be estimated by the calculated velocity field and the crust thickness, respectively.
- and K-montmorillonite川喜田 竜平; 齋藤 彬人*; 佐久間 博*; 安楽 総太郎; 菊池 亮佑*; 大竹 翼*; 佐藤 努*
Applied Clay Science, 231, p.106722_1 - 106722_7, 2023/01
被引用回数：7 パーセンタイル：43.02(Chemistry, Physical)Montmorillonite (Mt) expansion and swelling are key factors for barrier performance of bentonite in trans-uranic (TRU) and high-level radioactive waste disposals. In the case of co-located geological disposal of TRU waste with high level waste, ammonium ion (NH
) which is changed from nitrate ion leached from TRU waste has possibility to contact with bentonite, exchange interlayer cation of Mt to form NH-Mt, and deteriorate its performance. Because of similar hydration energy of NH to K, NH-Mt could have lower expandability or change to non-expandable mineral as reported on K-Mt. Therefore, expansion and alteration behaviors of NH-Mt, especially comparison to the behaviors of K-Mt, are necessary to understand for safety assessment of the waste disposal. In this study, the hydration behavior of NH-Mt was investigated by XRD and molecular dynamics (MD) simulation in comparison with K-Mt. XRD profiles under Relative Humidity (RH) control showed that expansion of NH-Mt was similar to that of K-Mt at more than RH40% with slightly different d-values. However, expansion of NH-Mt kept at lower than RH20%, while K-Mt easily dehydrate at the same RH. MD simulation revealed that hydrogen bonding (HB) in NH molecules causes the difference in hydration behavior between NH- and K-Mt, as HB cause larger basal spacing at dehydrated state and easier hydration. This gap on hydration may attribute the difference in alteration to non-expandable minerals after dehydration, indicating that NH have lower possibility for alternation and smaller effect on barrier performance of bentonite than K.
岩本 修; 岩本 信之; 国枝 賢; 湊 太志; 中山 梓介; 安部 豊*; 椿原 康介*; 奥村 森*; 石塚 知香子*; 吉田 正*; et al.
Journal of Nuclear Science and Technology, 60(1), p.1 - 60, 2023/01
被引用回数：397 パーセンタイル：99.99(Nuclear Science & Technology)The fifth version of Japanese Evaluated Nuclear Data Library, JENDL-5, was developed. JENDL-5 aimed to meet a variety of needs not only from nuclear reactors but also from other applications such as accelerators. Most of the JENDL special purpose files published so far were integrated into JENDL-5 with revisions. JENDL-5 consists of 11 sublibraries: (1) Neutron, (2) Thermal scattering law, (3) Fission product yield, (4) Decay data, (5) Proton, (6) Deuteron, (7) Alpha-particle, (8) Photonuclear, (9) Photo-atomic, (10) Electro-atomic, and (11) Atomic relaxation. The neutron reaction data for a large number of nuclei in JENDL-4.0 were updated ranging from light to heavy ones, including major and minor actinides which affect nuclear reactor calculations. In addition, the number of nuclei of neutron reaction data stored in JENDL-5 was largely increased; the neutron data covered not only all of naturally existing nuclei but also their neighbor ones with half-lives longer than 1 day. JENDL-5 included the originally evaluated data of thermal scattering law and fission product yield for the first time. Light charged-particle and photon induced reaction data were also included for the first time as the JENDL general purpose file.
