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Li, X.; 山路 哲史*; 佐藤 一憲*; 山下 拓哉
Annals of Nuclear Energy, 214, p.111217_1 - 111217_13, 2025/05
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)The decommissioning of Fukushima Daiichi NPP Unit-2 requires understanding of reactor damage and fuel debris distribution for effective debris retrieval. This study numerically analyzes potential Reactor Pressure Vessel (RPV) boundary failure due to eutectic melting of Control Rod Drive (CRD) housings during reheating after debris bed dryout. The Moving Particle Semi-implicit (MPS) method, with an enthalpy-based temperature algorithm and Boussinesq approximation, is applied to simulate melt/solid interactions in a 2-D model of the lower plenum. The CRD housing melting temperature is set at 1523 K based on a quasi-binary phase diagram of 304 Stainless Steel (SS) and Zirconium (Zr) and ELSA experiments. Results suggest local RPV failure at CRD housings, leading to melt release and refreezing. The estimated failure occurs 8-12 hours post-dryout (ca. 12:00-16:00 on 3/15/2011), providing insights into melt progression and boundary breach scenarios in Unit-2.
佐藤 達彦; 古田 琢哉; 佐々木 秀隆*; 渡部 直史*
EJNMMI Physics (Internet), 12, p.28_1 - 28_16, 2025/03
被引用回数：0 パーセンタイル：0.00(Radiology, Nuclear Medicine & Medical Imaging)The RadioTherapy package based on PHITS (RT-PHITS) is one of the individual dosimetry systems applicable to both targeted radionuclide therapy (TRT) and external radiotherapy. This study aims to establish a practical methodology for evaluating both absorbed doses and equieffective doses (EQDX) by improving RT-PHITS.
Lu-DOTATATE peptide receptor radionuclide therapy三輪 建太*; 柿野 諒*; 佐藤 達彦; 古田 琢哉; 宮司 典明*; 山尾 天翔*; 山下 康輔*; 寺内 康輔*
Physical and Engineering Sciences in Medicine, 9 Pages, 2025/00
被引用回数：0RT-PHITSは、PHITSを放射線治療分野に応用するための統合パッケージで、患者のCT/SPECT画像をPHITSの入力形式に変換してその線量評価を行うことができる。本稿では、Lu-DOTATATEペプチド受容体核医学療法後のSPECT/CT画像とRT-PHITSを用いた個別線量測定の実現可能性について検討する。
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。
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*
International Journal of Pressure Vessels and Piping, 211, p.105298_1 - 105298_6, 2024/10
Passive safety structures were applied to next-generation fast reactors, subject to high temperature and low-pressure conditions. In the case of loss-of-heat-removal accidents, high temperature conditions accelerate the creep deformation of structures. When deformation redistributes loadings and reduces stresses at important positions such as coolant boundaries, progression to creep rupture of boundaries can be mitigated. When an excessive earthquake occurs, plastic deformation and buckling become dominant, due to low pressure and, therefore, a thin-wall structure. The above-mentioned failure modes reduce rigidity and natural frequency. When the natural frequency becomes lower than the input frequency, vibration energy is hardly transferred to structures and the subsequent failures of structures, such as collapse and break, are mitigated.
佐藤 薫; 古田 琢哉; 佐藤 大樹; 津田 修一
PLOS ONE (Internet), 19(10), p.e0309753_1 - e0309753_26, 2024/10
被引用回数：0 パーセンタイル：0.00(Multidisciplinary Sciences)これまでに、放射線事故や医療被ばくの線量評価を目的とした数値ファントムとして、標準日本人体型の成人男性(JM-103)及び成人女性(JF-103)のボクセルファントムを開発した。しかし、JM-103及びJF-103は記述形式や解像度の制約により、被ばく時の姿勢を考慮した線量評価に対応できない課題があった。そこで本研究では、JM-103及びJF-103をベースとして、柔軟な変形が可能なポリゴンメッシュ形式の成人日本人ファントム(男性:JPM、女性:JPF)を開発した。JPM及びJPFには、1mm厚以下の微小な放射性感受性領域を有する皮膚及び水晶体の詳細モデルが組み込まれている。光子または電子を外部から前方照射する場合について、実効線量、皮膚及び水晶体(全領域及び放射性感受性領域)の線量を計算した結果、皮膚及び水晶体の全領域の計算結果について、JPM及びJPFはJM-103及びJF-103及びICRP等の文献値と矛盾しないことを確認した。さらに、これまで計算できなかった放射線感受性の高い微小な部位における線量を計算するとともに、その入射エネルギー依存性評価が可能となった。今後、構築したJPM及びJPFに現在開発中の姿勢変形技術を適用することによって、被ばく時の姿勢を考慮した、個人に対する詳細な線量評価手法を開発する予定である。
and 
study of biological effects on cancer cells in the presence of metallic materials during radiotherapy長野 拓也*; 松谷 悠佑; 戒田 篤志*; 野島 瞳*; 古田 琢哉; 佐藤 薫; 吉村 亮一*; 三浦 雅彦*
Journal of Radiation Research (Internet), 65(5), p.628 - 639, 2024/09
被引用回数：0 パーセンタイル：0.00(Biology)X線治療では、正常組織への副作用を最小限に抑えつつ腫瘍を治療するように照射計画が計画される。頭頚部への放射線照射により、歯の金属製の詰め物周辺において重度の粘膜炎(放射線増感作用)が誘発されることがある。しかしながら、この放射線増感メカニズムは不明なままである。本研究では、細胞実験と計算シミュレーションを使用して放射線増感メカニズムを調査した。その結果、細胞実験で観測された増感比は1.2-1.4であり、これは金属近傍の局所線量増加が主要因であることがわかった。一方、臨床前試験としてCT画像に基づく生体内線量評価を実施した結果、人体の複雑な解剖構造により線量増加が過小評価され、微視的な線量評価が必要であることが分かった。本成果は、金属周辺における正常細胞への副反応の正確な理解に貢献するものである。
C
reaction at 1.8 GeV/
with the Superconducting Kaon spectrometer市川 裕大; 藤田 真奈美; 長谷川 勝一; 今井 憲一*; 七村 拓野; 成木 恵; 佐藤 進; 佐甲 博之; 田村 裕和; 谷田 聖; et al.
Progress of Theoretical and Experimental Physics (Internet), 2024(9), p.091D01_1 - 091D01_13, 2024/09
被引用回数：0 パーセンタイル：0.00(Physics, Multidisciplinary)We conducted a measurement of the inclusive missing-mass spectrum in the C
reaction at an incident beam momentum of 1.8 GeV/. This measurement was carried out utilizing the Superconducting Kaon Spectrometer (SKS) and the K1.8 beamline spectrometer at the Hadron Experimental Hall in J-PARC. Remarkably, our experimental setup yielded an exceptionaly good energy resolution of 8.2 MeV (FWHM), enabling us to observe significant enhancements in the vicinity of the 
Be threshold region. In order to estimate the spectrum information, we employed several fitting parameters assumptions. The best agreement with the spectrum shape was obtained with combining quasi-free (QF) component and two-Gaussian functions, with the experimental resolution 
being held constant. The peak positions were obtained to be 
(stat.) 
(syst.) MeV and 
(stat.) 
(syst.) MeV. Another model assumption, utilizing quasi-free (QF) and one Breit-Wigner function with 
(stat.) 
(syst.) MeV and 
(stat.) 
(syst.) MeV, also yielded a similar 
value.
佐藤 一憲; 吉川 信治; 山下 拓哉; 下村 健太; Cibula, M.*; 溝上 伸也*
Nuclear Engineering and Design, 422, p.113088_1 - 113088_24, 2024/06
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)The accident progression of the in-vessel phase of Fukushima Daiichi Nuclear Power Station Unit 1 was analyzed using the MAAP code. Although there is a large uncertainty in the initial stage of accident progression behavior in Unit 1 with little measurement data, it is presumed to have similarities to that of Unit 3. As a result, in Unit 1, since there was almost no alternative water injection during the in-vessel phase, cooling of the debris transferred to the lower plenum was small. It was likely that a large molten pool of metals had formed, and that the steam supply to the high-temperature core materials was suppressed and metal oxidation was relatively small. The analysis results for Unit 1 were compared with those for Units 2 and 3, and differences between units such as the thermal conditions of the debris that relocated to the pedestal and the degree of metal oxidation were shown.
石川 諒尚; 古場 裕介*; 古田 琢哉; Chang, W.*; 米内 俊祐*; 松本 真之介*; 橋本 慎太郎; 平井 悠大*; 佐藤 達彦
Radiological Physics and Technology, 17(2), p.553 - 560, 2024/06
At the Heavy Ion Medical Accelerator in Chiba (HIMAC), a series of retrospective studies are ongoing in patients treated with carbon ion radiotherapy (CIRT) to obtain the knowledge to improve tumor control and reveal the mechanism of the low risk of secondary cancer after CIRT. Dose-averaged linear energy transfer (LET
) is generally used as a measure of treatment effectiveness or biological effects in such retrospective studies; however, it is conventionally evaluated from the relative biological effectiveness (RBE)-LET fitted function used in the treatment planning system. In this study, we calculated the physical doses and their linear energy transfer (LET) distributions for a series of treatment plans for a homogeneous rectangular phantom and a human body phantom with typical CIRT beams using Monte Carlo (MC) simulation. The LET was then deduced from the MC simulation and compared with the corresponding data obtained using the conventional method. The comparison suggested that the two types of LET agreed well with each other, except around the distal end of the spread-out Bragg peak, where the MC simulation yielded significantly higher LET values than that of the conventional method. This is because the RBE-LET fitted function adopted in the conventional method ignores the contribution of the high-LET components, causing an overkill effect. Furthermore, an MC simulation was conducted to determine the material composition of water and realistic materials from the CT number in the planned image. The profiles of physical dose and LET were in good agreement for both techniques. These results indicate the possibility of enhancing the efficiency of retrospective studies of CIRT using MC simulations in the future.
Li, X.; 山路 哲史*; 佐藤 一憲*; 山下 拓哉; 永江 勇二
Proceedings of 11th European Review Meeting on Severe Accident Research Conference (ERMSAR 2024) (Internet), 12 Pages, 2024/05
For Fukushima Daiichi Nuclear Power Station (1F) Unit-2, the muon radiography investigation results indicate that the fuel debris are largely retained inside the RPV. The current study focuses on the analysis of metallic melt penetration behavior in the CRD housing with Moving Particle Semi-implicit (MPS) method. A three-dimensional CRD housing model with simplified inner structures was established. The injection of SS-Zircaloy eutectic melt into the CRD housing was simulated and its downstream penetration and freezing behavior under vertically varying temperature boundary conditions was analyzed. It is found that the melt would start to freeze and form channel blockages soon after it enters the region with a relatively cold boundary in the downstream.
C ions based on first-principles calculations関川 卓也; 松谷 悠佑; Hwang, B.*; 石坂 優人*; 川井 弘之*; 大野 義章*; 佐藤 達彦; 甲斐 健師
Nuclear Instruments and Methods in Physics Research B, 548, p.165231_1 - 165231_6, 2024/03
被引用回数：1 パーセンタイル：58.81(Instruments & Instrumentation)放射線の人体に与える影響の主な原因として、遺伝情報を担うDNAの損傷が考えられている。しかし、DNAが放射線損傷によりどのような分子構造変化を示すかは十分理解されていない。DNAに放射線を照射すると様々な種類のDNA損傷が形成されることが報告されていることから、我々のグループではDNAが受ける損傷と放射線によって引き起こされる様々なパターンのイオン化の関係を調べてきた。これまでDNAを模した剛体モデルを用いた簡易な体系における解析を行っていたが、人体への影響を考える上で重要と考えられるDNAの分子構造変化を解析するためにはより詳細な計算を必要とする。そこで、本研究では分子構造に基づいて電子状態を議論できる第一原理計算ソフトウェアOpenMXを用いてDNAの分子構造変化を明らかにすることを試みた。具体的には、放射線により1電子及び2電子が電離した状況のDNAを仮定し、最安定構造、バンド分散、及び波動関数を計算した。発表では、粒子・重イオン輸送計算コードPHITSを用いて計算した放射線の線種及びエネルギーとDNAの分子構造変化の関係とともに議論する。また、放射線物理・固体物理の双方の観点から、放射線がもたらすDNAの基礎物性変化(DNA損傷の最初期過程に相当)について議論する。
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。
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：129 パーセンタイル：99.97(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。
佐藤 一憲; 吉川 信治; 山下 拓哉; 下村 健太; Cibula, M.*; 溝上 伸也*
Nuclear Engineering and Design, 414, p.112574_1 - 112574_20, 2023/12
Based on the updated knowledge from plant-internal investigations, experiments and computer-model simulations until now, the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 3 was analyzed using the MAAP code. In Unit 3, it is considered that ca. 40 percent of UO
fuel was molten when core materials relocated to the lower plenum of the reactor pressure vessel. Initially relocated molten materials would have been fragmented by mixing with liquid water, while solid materials would have relocated later on. With this two-step relocation, debris in the lower plenum seems to have been permeable for coolant, thus debris seems to have been once cooled down effectively. Although the present MAAP analysis seems to slightly underestimate core-material oxidation during the relocation period, this probable underestimation was compensated for by an existing study that was considered more reliable, so that more realistic debris conditions in the lower plenum could be obtained. Probable debris reheat-up behavior was evaluated based on interpretation of the pressure data. This evaluation predicted that the fuel debris in the lower plenum was basically in solid-phase at the time when it relocated to the pedestal. With this study, basic validity of the former prediction of the Unit 3 accident progression behavior was confirmed, and detailed boundary conditions for future studies addressing the later phases were provided.
山下 拓哉; 本多 剛*; 溝上 暢人*; 野崎 謙一朗*; 鈴木 博之*; Pellegrini, M.*; 酒井 健*; 佐藤 一憲; 溝上 伸也*
Nuclear Technology, 209(6), p.902 - 927, 2023/06
被引用回数：5 パーセンタイル：80.64(Nuclear Science & Technology)The estimation and understanding of the state of fuel debris and fission products inside the plant is an essential step in the decommissioning of the TEPCO Fukushima Daiichi Nuclear Power Station (1F). However, the direct observation of the plant interior, which is under a high radiation environment, is difficult and limited. Therefore, in order to understand the plant interior conditions, a comprehensive analysis and evaluation is necessary, based on various measurement data from the plant, analysis of plant data during the accident progression phase and information obtained from computer simulations for this phase. These evaluations can be used to estimate the conditions of the interior of the reactor pressure vessel (RPV) and the primary containment vessel (PCV). Herein, 1F Unit 3 was addressed as the subject to produce an estimated diagram of the fuel debris distribution from data obtained about the RPV and PCV based on the comprehensive evaluation of various measurement data and information obtained from the accident progression analysis, which were released to the public in November 2022.
佐藤 一憲; 吉川 信治; 山下 拓哉; Cibula, M.*; 溝上 伸也*
Nuclear Engineering and Design, 404, p.112205_1 - 112205_21, 2023/04
被引用回数：10 パーセンタイル：95.46(Nuclear Science & Technology)これまでのプラント内部調査、実験、コンピュータモデルシミュレーションから得られた最新の知見に基づき、福島第一原子力発電所2号機の原子炉圧力炉容器内フェーズに対するMAAP解析を実施した。2号機では、炉心物質が圧力容器の下部プレナムに移動し、そこで冷却材によって冷却されて固化したときのエンタルピーが比較的低かったと考えられる。MAAPコードは、炉心物質リロケーション期間中の炉心物質の酸化の程度を過小評価する傾向があるが、酸化に係るより信頼性の高い既存研究を活用することによって補正を行うことで、下部プレナム内の燃料デブリ状態の、より現実的な評価を行った。この評価により、2号機事故進展挙動に係る既往予測の基本的妥当性が確認され、今後の後続過程研究を進めるための詳細な境界条件を提供した。下部ヘッドの破損とペデスタルへのデブリ移行に至るデブリ再昇温プロセスに対処する将来研究に、本研究で得た境界条件を反映する必要がある。
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：2 パーセンタイル：29.47(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.
後神 利志*; 江端 健悟; 藤田 真奈美; 原田 健志; 長谷川 勝一; 細見 健二; 市川 裕大; 今井 憲一*; Kim, S.; 七村 拓野; et al.
EPJ Web of Conferences, 271, p.11002_1 - 11002_7, 2022/11
In the K1.8 beam-line at Hadron Experimental Facility of J-PARC, a new magnetic spectrometer S-2S is being installed. S-2S was designed to achieve a high momentum resolution of 
in FWHM. Several strangeness-physics programs which require the high resolution will be realized by S-2S. The present article introduces J-PARC E70 (missing-mass spectroscopy of 
Be) and E94 (missing-mass spectroscopy of 
Li, 
B, and 
C) experiments.
elastic scattering in the momentum range 0.44-0.80 GeV/c七村 拓野; 藤田 真奈美; 長谷川 勝一; 市川 真也; 市川 裕大; 今井 憲一*; 成木 恵; 佐藤 進; 佐甲 博之; 田村 裕和; et al.
Progress of Theoretical and Experimental Physics (Internet), 2022(9), p.093D01_1 - 093D01_35, 2022/09
被引用回数：16 パーセンタイル：83.44(Physics, Multidisciplinary)We performed a novel 
scattering experiment at the J-PARC Hadron Experimental Facility. Approximately 2400 elastic scattering events were identified from 
tagged 
particles in the momentum range 0.44 - 0.80 GeV/c. The differential cross sections of the elastic scattering were derived with much better precision than in previous experiments. The obtained differential cross sections were approximately 2 mb/sr or less, which were not as large as those predicted by the fss2 and FSS models based on the quark cluster model in the short-range region. By performing phase-shift analyses for the obtained differential cross sections, we experimentally derived the phase shifts of the 
and 
channels for the first time. The phase shift of the 3S1 channel, where a large repulsive core was predicted owing to the Pauli effect between quarks, was evaluated to be 
. If the sign of 
is assumed to be negative, the interaction in this channel is moderately repulsive, as the Nijmegen extended-sort-core models predicted.
