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外間 智規; 木村 仁宣; 外川 織彦
JAEA-Research 2023-010, 57 Pages, 2024/02
JAEA-Research-2023-010.pdf:3.29MB
原子力災害時に住民の甲状腺中放射性ヨウ素放射能の簡易測定を行うことが計画されている。簡易測定にはスクリーニングレベル:0.20
Sv/hが目安として設定されており、原子力災害等の状況に応じて適切に見直すこととされている。しかしながら、スクリーニングレベルの見直しに関する具体的な方針は定められていない。スクリーニングレベルの見直しについては、甲状腺内部被ばく線量の判断レベルや簡易測定の実施期間等、簡易測定の可否に係る要因について考慮する必要がある。本研究では、スクリーニングレベル:0.20Sv/hの設定根拠を整理するとともに、原子力災害時におけるスクリーニングレベル見直しの実行性について考察を行った。スクリーニングレベルを0.025
0.50Sv/hの範囲で見直した場合の判断レベルと実施期間との関係を計算し、スクリーニングレベル見直しの実行性について考察を行った。その結果、スクリーニングレベルの見直しについては、適切な判断レベルと実施期間を選択しなければならないという技術的な制約はあるものの実行可能であることが分かった。しかしながら、原子力災害時の簡易測定の実際を想定した場合、スクリーニングレベル見直しについては、実施期間の延長が必要な状況において0.0300.20Sv/hの範囲で設定することが妥当であろうと評価した。
-Mo
O
revealed by angle-resolved photoelectron spectroscopy and first-principles calculation角田 一樹; 檜垣 聡太*; 佐藤 仁*; 水流 大地*; 宮本 幸治*; 奥田 太一*; 黒岩 芳弘*; 森吉 千佳子*; 高瀬 浩一*; 小口 多美夫*; et al.
Journal of the Physical Society of Japan, 92(8), p.084706_1 - 084706_6, 2023/08
被引用回数：0 パーセンタイル：0(Physics, Multidisciplinary)We investigated the electronic structure of -MoO bulk crystal in the whole Brillouin zone at a normal metallic state by utilizing resonant and angle-resolved photoelectron spectroscopies and first-principles calculations. Mo 4
-4
resonant photoelectron experiment revealed that the Mo 4 electrons of MoO
octahedra mainly contributed to the electrical conductivity. We also demonstrated that the free electron-like band dispersions along 
axis, consisting of Mo 4
electrons, do not show clear 
and 
dependences and formed a one-dimensional Fermi surface even at the normal state. The observed low-dimensional and anisotropic band structures are expected to induce exotic physical properties such as quantized bulk Hall effect, charge density wave transitions, and Luttinger liquid behavior.
永井 佑哉; 周治 愛之; 川崎 猛; 會田 貴洋; 木村 泰久; 根本 靖範*; 小沼 武司*; 冨山 昇*; 平野 耕司*; 薄井 康弘*; et al.
JAEA-Technology 2022-039, 117 Pages, 2023/06
JAEA-Technology-2022-039.pdf:11.96MB
日本原子力研究開発機構は多くの原子力施設を保有しているが、その多くで老朽化・高経年化への対応、東日本大震災及び福島第一原子力発電所の事故を受けた耐震化や新規制基準への対応が求められ、多額の予算を要する状況である。このため、役割を終えた原子力施設についても根本的なリスク低減及び維持管理費用の削減のために施設の廃止措置を進めることが望ましいが、廃止措置及び発生する放射性廃棄物の処理処分に必要な施設の整備・維持管理にも多額の費用が必要となる。この状況を踏まえ、原子力機構では(1)継続利用する施設を絞り込む「施設の集約化・重点化」、(2)新規制基準・耐震化対応、高経年化対策、リスク低減対策等の「施設の安全確保」及び(3)廃止措置、廃棄物の処理処分といった「バックエンド対策」を3つの柱とした「施設中長期計画」を策定した。本計画において、プルトニウム燃料第二開発室は廃止施設として位置付けられており、施設内に設置された設備の解体撤去を進めている。今回の解体撤去対象は、焙焼還元炉、ペレット粉砕設備、これらを包蔵するグローブボックスNo.W-9及びW-9と隣々接の工程室内に設置されているグローブボックスNo.D-1とを連結するトンネル形状のグローブボックスNo.F-1の一部であり、許認可等による約4年の作業中断期間を含めて平成26年2月から令和2年2月の約6年間をかけて作業を実施した。本報告書では、本解体撤去における作業実績、解体撤去を通して得られた知見をまとめたものである
Am neutron capture cross section in the keV region using Si and Fe-filtered neutron beamsRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*
Journal of Nuclear Science and Technology, 60(5), p.489 - 499, 2023/05
被引用回数：2 パーセンタイル：53.91(Nuclear Science & Technology)The neutron capture cross-section of Am was measured in the keV neutron range using the recently implemented neutron filtering system of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). Filter arrays consisting of 20 cm of 
Fe and Si were employed in separate measurements to provide filtered neutron beams with averaged neutron energies of 23.5 (Fe), 51.5 and 127.7 (Si) keV. The present Am results were obtained relative to the 
Au neutron capture yield by applying the total energy detection principle together with the pulse-height weighting technique. The Am neutron capture cross section was determined as 2.72 
0.29 b at 23.5 keV, 2.14 0.26 b at 51.5 keV and 1.32 0.10 b at 127.7 keV with total uncertainties in the range of 8 to 12
, much lower in comparison to the latest time-of-flight experimental data available.
片渕 竜也*; 岩本 修; 堀 順一*; 木村 敦; 岩本 信之; 中村 詔司; Rovira Leveroni, G.; 遠藤 駿典; 芝原 雄司*; 寺田 和司*; et al.
EPJ Web of Conferences, 281, p.00014_1 - 00014_4, 2023/03
Long-lived minor actinides (MA) in nuclear waste from nuclear power plants are a long-standing issue to continue nuclear energy production. To solve the issue, researchers have suggested nuclear transmutation, in which long-lived radionuclides are transmuted into stable or shorter-life nuclides via neutron-induced nuclear reactions. Development of nuclear transmutation systems as an accelerator-driven system requires accurate neutron nuclear reaction data. The present research project entitled "Study on accuracy improvement of fast-neutron capture reaction data of long-lived MAs for development of nuclear transmutation systems" have been conducted as a joint collaboration, including Tokyo Tech, Japan Atomic Energy Agency and Kyoto University. This project focuses on the neutron capture reaction of MAs, especially 
Np, Am and 
Am, in the fast neutron energy region. The final goal of this project is to improve the accuracies of the neutron capture cross sections of Np, Am and Am employing a high-intensity neutron beam from a spallation source of the Japan Proton Accelerator Research Complex (J-PARC) that reduces uncertainties of measurement. To achieve the goal, a neutron beam filter system in J-PARC, sample characteristic assay, and theoretical reaction model study were developed. In this contribution, the overview and results of the project will be presented.
外川 織彦; 大倉 毅史; 木村 仁宣
JAEA-Review 2022-049, 76 Pages, 2023/01
JAEA-Review-2022-049.pdf:3.74MB
原子力施設の建設前及び操業開始後には、平常運転時及び事故時に対する環境影響評価が行われる。これらは、周辺住民の安全の確認と安心の醸成を図ることを主たる目的としている。環境影響評価には、施設周辺の環境モニタリング等による観測・測定と計算モデルによるモデル推定が用いられ、状況や必要性などに応じてそれらのどちらか、あるいは両方を併用して実施される。本報告書では、原子力施設の環境影響評価において利用される観測・測定とモデル推定について、青森県六ヶ所村再処理施設を主たる例として、まず各々の方法、役割と長短、相互の関係性を調査する。次に、観測・測定データとモデル推定結果の代表的な用途例を示し、使用に際しての留意点などを検討する。最後に、観測・測定とモデル推定の高度化や両者の融合という今後の方向性を記述する。
Am neutron capture cross section measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*
Journal of Nuclear Science and Technology, 19 Pages, 2023/00
被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)The neutron capture cross-section of Am was measured from 10 meV to about 1 MeV using the NaI(Tl) spectrometer of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). The total energy detection principle was applied in conjunction with the pulse-height weighting technique to derive the neutron capture yield. The present cross-section results were normalized using a Au sample measurement by applying the saturated resonance method. The thermal cross section was measured to be 708 22 b, in agreement within uncertainties to the present evaluation in JENDL-5 of 709 b. Moreover, the results of a shape resonance analysis of the resolved resonance region are also provided in the present dissertation.
中野 秀仁*; 片渕 竜也*; Rovira Leveroni, G.; 児玉 有*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典
Journal of Nuclear Science and Technology, 59(12), p.1499 - 1506, 2022/12
被引用回数：1 パーセンタイル：31.61(Nuclear Science & Technology)A neutron monitoring detection system was developed for neutron capture cross section measurement using a spallation neutron source. A combination of a plastic scintillator and a thin 
LiF foil was adopted for the detector. The detector system was tested to study the feasibility of the system. Neutron irradiation experiments were conducted with the Accurate Neutron-Nucleus Reaction Measurement Instrument in the Materials and Life Science facility of the Japan Proton Accelerator Research Complex. A neutron time-of-flight spectrum was successfully measured without significant count loss or detector paralysis. The statistical uncertainty reached 0.7% at neutron energies around 6 meV.
Am neutron capture cross section measurement and resonance analysisRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*
JAEA-Conf 2022-001, p.91 - 96, 2022/11
Neutron capture cross section measurements were performed in the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Materials and Life Science Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC). The time-of-flight (TOF) methodology was employed in a non-filter condition experiment to determine the neutron capture cross section from thermal to about 100 eV. Moreover, experiments were performed using the neutron filtering system to determine the neutron capture cross section at the energy of 23.5 keV using Fe as filter material. In this study, the preliminary results of the Am neutron capture cross section from 10 meV to about 100 eV determined in TOF experiments and at 23.5 keV from Fe filter experiments are presented. In the TOF experiments, the Am neutron capture cross section was normalized by means of the saturated resonance method using a Au sample with a mass of 1.5 g. In addition, for the Fe filter experiments, the capture cross section of Am at the energy of 23.5 keV was determined relative to the Au yield obtained from a measurement using the same Au sample. Moreover, early-stage results of a resonance analysis of the Am capture resonances are also presented.
Au with a Cr-filtered neutron beam at the ANNRI beamline of MLF/J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*; et al.
Journal of Nuclear Science and Technology, 59(5), p.647 - 655, 2022/05
被引用回数：1 パーセンタイル：16.35(Nuclear Science & Technology)Cr-filtered keV-neutron experiments were performed in the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC) to measure the neutron capture cross-section of Au. The energy range of the neutron filtering system at ANNRI was extended through the use of 15 cm of Cr as filter material to tailor quasi-monochromatic neutron peaks with averaged neutron energies of 133.4 and 45.0 keV. The performance of the Cr filter assembly was evaluated by means of experimental capture and transmission analyses, together with the use of Monte-Carlo simulations. The present Au neutron capture cross-section results provide agreement within uncertainties with the JENDL-4.0 standard evaluated library and the IAEA standard data library further demonstrating the capabilities of the neutron filtering system at ANNRI.
木村 郁仁*; 山村 聡太*; 藤原 広太*; 吉田 啓之; 齋藤 慎平*; 金子 暁子*; 阿部 豊*
Nuclear Engineering and Design, 389, p.111660_1 - 111660_11, 2022/04
被引用回数：3 パーセンタイル：68.71(Nuclear Science & Technology)A new three-dimensional laser-induced fluorescent (3D-LIF) technology to obtain the hydrodynamic behavior of liquid jets in a shallow pool were developed. In this technology, firstly, a refractive index matching was applied to acquire a clear cross-sectional image. Secondly, a series of cross-sectional images was obtained by using a high-speed galvanometer scanner. Finally, to evaluate the unsteady 3D interface shape of liquid jet, a method was developed to reconstruct 3D shapes from the series of cross-sectional images obtained using the 3D-LIF method. The spatial and temporal resolutions of measurement were 4.7 
4.7 1.0 lines/mm and 25 s, respectively. The shape of a 3D liquid jet in a liquid pool and its impingement, spreading and atomization behavior were reconstructed using the proposed method, successfully. The behaviors of atomized particles detached from the jet were obtained by applying data processing techniques. Diameters distribution and position of atomized droplets after detachment were estimated from the results.
Rovira Leveroni, G.; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之; 遠藤 駿典; 片渕 竜也*; 寺田 和司*; 児玉 有*; 中野 秀仁*; et al.
JAEA-Conf 2021-001, p.156 - 161, 2022/03
A neutron filtering system has been designed in order to bypass the double-timed structure of the beam. Filter materials were introduced into the rotary collimator of the ANNRI beamline in order to produce quasi-monoenergetic neutron filtered beams. Filter assemblies consisting of Fe with a thickness of 20 cm, and Si with thicknesses of 20 cm and 30 cm of Si were used separately to produce filtered neutron peaks with energies of 24 keV (Fe) and of 54 and 144 (Si). In this study, the characteristics and performance of the neutron filtering system at ANNRI using Fe and Si determined from both measurements and simulations are presented. The incident neutron flux was tested and analyzed by means of transmission and capture experiments. Moreover, simulations using the PHITS code were performed in order to determine the energy distribution of the integrated filtered peaks and assess the reliability of experimental results. Finally, preliminary results of the capture cross section of Au at the filtered energies of 24, 54 and 144 keV are also presented using the NaI(Tl) spectrometer alongside the neutron filtering system.
中野 秀仁*; 片渕 竜也*; Rovira Leveroni, G.*; 児玉 有*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典
JAEA-Conf 2021-001, p.166 - 170, 2022/03
In neutron capture cross section measurement, monitoring the number of the incident neutrons is necessary. However, in measurement with J-PARC/ANNRI, direct neutron monitoring system has not been employed. Conventional neutron detectors cannot be used as a beam monitor at ANNRI because of two reasons, high counting rate environment and gamma-flash. In general, a semiconductor detector or an inorganic scintillator, which is adopted for a neutron detector, has relatively longer response time and is unsuitable for beam monitoring at ANNRI. Therefore, a combination of a thin plastic scintillator and a LiF foil was selected as a detection system, whose fast response enabled detecting neutrons at a high counting rate. Low gamma ray sensitivity of a thin plastic scintillator allows measuring fast TOF region without count loss or detector paralysis. The geometry of the LiF foil, the plastic scintillator, and photomultiplier tube (PMT) was designed. The optimal thickness of the LiF foil was determined with simulation codes, SRIM and PHITS. The detector system was tested under the high neutron irradiation condition at J-PARC /ANNRI. A neutron TOF spectrum was successfully measured without significant count loss or detector paralysis. A neutron energy spectrum was driven from difference of TOF spectrum with and without LiF. The neutron spectrum was compared with a past neutron spectrum and good agreement was obtained. Statistic error was 0.68 at 6.0 meV even though measurement times in this study were short.
児玉 有*; 片渕 竜也*; Rovira Leveroni, G.; 中野 秀仁*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典
JAEA-Conf 2021-001, p.162 - 165, 2022/03
Precise nuclear data for neutron-induced reactions are necessary for the design of nuclear transmutation systems. Nevertheless, current uncertainties of nuclear data for minor actinide (MA) does not achieve requirements for the design of transmutation facilities. The determination of an incident neutron flux for measurements of neutron capture cross section is one of the main causes that affect the final uncertainty of the cross section results. In the present work, we suggest a new method to reduce systematic uncertainties of capture cross section measurements. The method employs change of the self-shielding effect with sample rotation angle. In capture cross section measurements in ANNRI, a boron sample is placed to determine the incident neutron spectrum by counting 478 keV 
-ray from the 
reaction. In this method, the boron sample is tilted with respect to the neutron beam direction, thereby changing the effective area. This results in change of the shapes of time-of-flight (TOF) spectrum of 478 keV -ray from the reaction with the tilted angle. Comparing the difference of the TOF spectra at different angles and assuming the 1/v energy dependence of cross section of the reaction, the area density of the boron sample can be determined without using the sample mass and area. Theoretical and experimental studies on the new method are ongoing. Calculation using Monte Carlo simulation code PHITS were carried out to study the feasibility of the present method. Test experiments using a sample rotation system at ANNRI were also performed.
NpRovira Leveroni, G.; 片渕 竜也*; 登坂 健一*; 松浦 翔太*; 児玉 有*; 中野 秀仁*; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之
Journal of Nuclear Science and Technology, 59(1), p.110 - 122, 2022/01
被引用回数：3 パーセンタイル：45.99(Nuclear Science & Technology)Neutron capture cross-section measurements for Np have been conducted with the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Materials and Life Science Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC) using neutrons with energy ranging from thermal energy to 1 MeV. A Time of Flight (TOF) method using a NaI(Tl) detector was employed for these measurements and the data were analyzed based on the pulse-height weighting technique in order to derive the neutron capture cross-section. The absolute capture cross-section was determined using the whole shape of the first resonance from JENDL-4.0 together with the total neutron flux derived from a Au sample measurement in which the first resonance was completely saturated. Both normalization techniques present agreement within 2%. The present results are also compared evaluated data libraries. There is a discrepancy of 10-25% discrepancy from 0.5 to 20 keV with JENDL-4.0. Nonetheless, above this energy, the JENDL-4.0 seems to reproduce the present data better as the results agree within uncertainties up to 500 keV. The cross-section results contain errors below 4% from 0.5 to 30 keV. However, the total uncertainty increases to over 8% over that energy. Along with the cross section measurement, theoretical calculations were performed to reproduce the present results.
林田 健志*; 上村 洋平*; 木村 健太*; 松岡 悟志*; 萩原 雅人; 廣瀬 左京*; 盛岡 仁*; 長谷川 達夫*; 木村 剛*
Physical Review Materials (Internet), 5(12), p.124409_1 - 124409_10, 2021/12
被引用回数：17 パーセンタイル：80.41(Materials Science, Multidisciplinary)The ferroaxial order, which is characterized by a rotational structural distortion in a crystal, has been recently proposed as one of ferroic orders. Though the domain formation is a characteristic feature in ferroic materials, there has been little study done concerning that for the ferroaxial order. Here, we investigate ferroaxial domains that are formed through a ferroaxial transition in two representative ferroaxial materials, NiTiO
and RbFe(MoO
)
. We spatially resolve their domain structures using an optical method based on electric-field- induced optical rotation, that is, electrogyration (EG). In NiTiO, multi-domains are constructed when crystals undergo a ferroaxial transition and the domain size depends on the cooling rate around the transition temperature. Furthermore, the ferroaxial domain structure obtained by the EG measurement is well matched with that by scanning X-ray diffraction (XRD). RbFe(MoO) also exhibits multi-domain states in which domain patterns are different each time a crystal undergoes a ferroaxial transition. In addition, the temperature dependence of the EG signal well obeys that of the order parameter of a first-order phase transition. These results ensure the effectiveness of the EG effect to elucidate the nature of ferroaxial order.
外川 織彦; 大倉 毅史; 木村 仁宣; 永井 晴康
JAEA-Review 2021-021, 61 Pages, 2021/11
JAEA-Review-2021-021.pdf:3.72MB
東京電力(株)福島第一原子力発電所事故を契機として、原子力防災への大気拡散モデルの利用について、様々な状況とレベルで論争は続いた。しかし、計算モデルによる予測は原子力災害対策に使用可能かどうかといった二者択一の極端な議論が多く、緊急時対応の科学的検証に基づいて丁寧に議論されてきたとは言い難かった。一方、日本原子力研究開発機構(原子力機構)内外には、大気拡散モデルやその解析結果の潜在的利用希望者が少なからず存在することが分かったが、複数の種類がある大気拡散モデルについて、その目的と用途に応じた使い分けに関して理解不足と誤解があることが見受けられた。本報告書では、原子力防災に利用される大気拡散モデルについて、原子力機構で開発または使用されているモデルを中心として、モデルの概要や計算手法等を比較するとともに、それらのモデルを利用した解析例を記述した。これにより、原子力機構内外における大気拡散モデルの潜在的利用希望者に対して、今後の検討や活動に参考となることを目的とした。
Am around 23.5 keV児玉 有*; 片渕 竜也*; Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 信之; 岩本 修; 堀 順一*; 芝原 雄司*; et al.
Journal of Nuclear Science and Technology, 58(11), p.1159 - 1164, 2021/11
被引用回数：4 パーセンタイル：56.94(Nuclear Science & Technology)The neutron capture cross section of Am was measured with a pulsed neutron beam from a spallation neutron source of the Japan Proton Accelerator Research Complex. A Fe neutron beam filter was used to make the incident neutron beam mono-energetic around 23.5 keV. The neutron capture -rays were detected with a NaI(Tl) detector. The pulse height weighting technique was employed to derive the neutron capture cross section from the pulse height spectrum. The cross section was determined relative to the capture cross section of Au of JENDL-4.0. The neutron capture cross section of Am was determined with a smaller uncertainty than previous measurements. The previous measurements and the JENDL-4.0 cross sections were found to be lower than the present result.
Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 寺田 和司*; 児玉 有*; 中野 秀仁*; et al.
Nuclear Instruments and Methods in Physics Research A, 1003, p.165318_1 - 165318_10, 2021/07
被引用回数：4 パーセンタイル：57.13(Instruments & Instrumentation)A neutron filtering system has been introduced in the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Material and Life Science (MLF) building of the Japan Proton Accelerator Research Complex (J-PARC) in order to produce quasi-monoenergetic neutron beams. The filtered neutron spectrum by the filter assemblies was analyzed by means of capture and transmission measurements and also by Monte Carlo simulations using PHITS. The characteristics of the filtered neutron beam are discussed alongside its viability in future applications for neutron cross-section measurements in the fast neutron region.
木村 仁宣; 小栗 朋美*; 石川 淳; 宗像 雅広
Journal of Nuclear Science and Technology, 58(3), p.278 - 291, 2021/03
被引用回数：1 パーセンタイル：12.16(Nuclear Science & Technology)原子力事故時の緊急時計画策定に資するため、レベル3PRAコードOSCAARを用いた緊急防護措置戦略の評価手法を開発した。OSCAARは、与えられた事故シナリオに対し、事故の初期段階に受ける被ばく線量を計算し、避難、屋内退避、安定ヨウ素剤の服用といった緊急防護措置の実施による被ばく低減効果を評価できる。本研究では、ある事故シナリオに対し、予防的防護措置を準備する区域(PAZ)及び緊急防護措置を準備する区域(UPZ)での緊急防護措置の組み合わせを検討し、これら防護措置を実施した際の被ばく線量をOSCAARで計算した。その後、OSCAARの防護措置モデルに対する感度解析を行い、国際原子力機関(IAEA)の包括的判断基準を下回る被ばく線量に低減させることで防護措置戦略を最適化した。結果として、PAZ内では予防的避難、UPZ内では屋内避難後に避難、コンクリート家屋または一般家屋での屋内退避、安定ヨウ素剤の服用を組み合わせることで、効果的な緊急防護措置戦略を策定することができた。本手法は、事故シナリオに応じた効果的な緊急防護戦略を策定する上で非常に有用である。
