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C powder and BC pellet regarding the eutectic reaction with stainless steelHong, Z.*; Ahmed, Z.*; Pellegrini, M.*; 山野 秀将; Erkan, N.*; Sharma, A. K.*; 岡本 孝司*
Progress in Nuclear Energy, 171, p.105160_1 - 105160_13, 2024/06
本研究では、BC粉末とステンレス鋼(SS)間との共晶反応はBC粉ペレットとSS間とのそれより相当に速いことが分かった。粉末及びペレットに対して導出された反応速度定数は参考文献値によく一致している。また、粉末とペレットの場合の詳細微細構造をSEM/EDSを用いて組成分析を行った。粉末の場合、(Fe,Cr)Bからなる反応層として厚肉層が見られた。一方、ペレットの場合、2つの反応層が見られた。
Baccou, J.*; Glantz, T.*; Ghione, A.*; Sargentini, L.*; Fillion, P.*; Damblin, G.*; Sueur, R.*; Iooss, B.*; Fang, J.*; Liu, J.*; et al.
Nuclear Engineering and Design, 421, p.113035_1 - 113035_16, 2024/05
In the Best-Estimate Plus Uncertainty (BEPU) framework, the use of best-estimate code requires to go through a Verification, Validation and Uncertainty Quantification process (VVUQ). The relevance of the experimental data in relation to the physical phenomena of interest in the VVUQ process is crucial. Adequacy analysis of selected experimental databases addresses this problem. The outcomes of the analysis can be used to select a subset of relevant experimental data, to encourage designing new experiments or to drop some experiments from a database because of their substantial lack of adequacy. The development of a specific transparent and reproducible approach to analyze the relevance of experimental data for VVUQ still remains open and is the topic of this contribution. In this paper, the concept of adequacy initially introduced in the OECD/NEA SAPIUM (Systematic APproach for model Input Uncertainty quantification Methodology) activity is formalized. It is defined through two key properties, called representativeness and completeness, that allows considering the multifactorial dimension of the adequacy problem. A new systematic approach is then proposed to analyze the adequacy of a set of experimental databases. It relies on the introduction of two sets of criteria to characterize representativeness and completeness and on the use of multi-criteria decision analysis method to perform the analysis. Finally, the approach is applied in the framework of the new OECD/NEA ATRIUM activity which includes a set of practical IUQ exercises in thermal-hydraulics to test the SAPIUM guideline in determining input uncertainties and forward propagating them on an application case. It allows evaluating the adequacy of eight experimental databases coming from the Super Moby-dick, Sozzi-Sutherland and Marviken experiments and identifying the most adequate ones.
民井 淳*; Pellegri, L.*; S
derstrm, P.-A.*; Allard, D.*; Goriely, S.*; 稲倉 恒法*; Khan, E.*; 木戸 英治*; 木村 真明*; Litvinova, E.*; et al.
European Physical Journal A, 59(9), p.208_1 - 208_21, 2023/09
被引用回数：1 パーセンタイル：0.02(Physics, Nuclear)光核反応は原子核構造の観点からも応用の観点からも重要であるにも関わらず、その反応断面積は未だに不定性が大きい。近年、超高エネルギー宇宙線の起源を探るために、鉄よりも軽い原子核の光核反応断面積を正確に知る必要が指摘されている。この状況を打破するため、原子核物理の実験、理論、宇宙物理の共同研究となるPANDORAプロジェクトが始まった。本論文はその計画の概要をまとめたものである。原子核実験ではRCNP、iThembaによる仮想光子実験とELI-NPによる実光子実験などが計画されている。原子核理論では、乱雑位相近似計算、相対論的平均場理論、反対称化分子動力学、大規模殻模型計算などが計画されている。これらで得られた信頼性の高い光核反応データベースと宇宙線伝搬コードを組み合わせ、超高エネルギー宇宙線の起源の解明に挑む。
Abeykoon, S.*; Howard, C.*; Dominijanni, S.*; Eberhard, L.*; Kurnosov, A.*; Frost, D. J.*; Boffa Ballaran, T.*; 寺崎 英紀*; 坂巻 竜也*; 鈴木 昭夫*; et al.
Journal of Geophysical Research; Solid Earth, 128(9), p.e2023JB026710_1 - e2023JB026710_17, 2023/09
被引用回数：0 パーセンタイル：0.01(Geochemistry & Geophysics)少量の硫化鉄鉱物は、地球のマントルから産出するほとんどの岩石や、天然のダイヤモンドに内包物として含まれている。水素は高温高圧下で硫化鉄鉱物に溶解している可能性があるが、地表の温度と圧力では失われている。本研究では、高温高圧下における硫化鉄中の重水素量を、11.4GPa, 1300Kまでの条件でJ-PARCのPLANETでの6軸型マルチアンビルプレスを用いたその場観察中性子回折実験により決定した。硫化鉄水素化物中の全重水素含有量は高温高圧下で増加することが明らかになった。この結果を用いて、大陸深部のリソスフェアマントル中の硫化鉄鉱物の水素含有量を見積もったところ、1700-2700ppmの範囲にあることがわかった。これはバルクマントル中の約2-3ppmの水素に相当する。
丸山 結; 杉山 智之*; 島田 亜佐子; Lind, T.*; Bentaib, A.*; Sogalla, M.*; Pellegrini, M.*; Albright, L.*; Clayton, D.*
Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (Internet), p.4782 - 4795, 2023/08
The Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi Nuclear Power Station (FDNPS) (ARC-F) project was initiated in January 2019 for three years with 22 signatories from 12 countries. Three main tasks were implemented in the ARC-F project, which were relevant to 1) refinement of analysis for accident scenarios and associated fission product (FP) transport and dispersion, 2) compilation and management of data and information, and 3) discussion for the next-phase project. Various activities were performed in Task 1, covering improvement of analysis for accident scenarios, and in-depth analyses for specific phenomena such as in-vessel melt progression, molten core/concrete interaction, FP transport and source term, hydrogen combustion and atmospheric dispersion of FPs. Through these studies, analyses for accident scenarios with severe accident codes were refined and important phenomena with large uncertainties were clarified. In order to share well selected and organized information from the FDNPS with the project partners, two databases, information source database and sample database, were built under Task 2. The analysis techniques including the separation of iodine species were developed also in Task 2 and applied to the analysis of FPs in several samples taken from the FDNPS. The next-phase project was discussed in Task 3, resulting in launching the Fukushima Daiichi Nuclear Power Station Information Collection and Evaluation (FACE) project. The FACE project officially started in July 2022 with the participation of 23 organizations from 12 countries and the European Commission.
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, 13 Pages, 2023/00
被引用回数：0 パーセンタイル：0.01(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 拓未; 永江 勇二; 倉田 正輝; Quaini, A.*; Gu
neau, C.*
CALPHAD; Computer Coupling of Phase Diagrams and Thermochemistry, 79, p.102481_1 - 102481_11, 2022/12
被引用回数：0 パーセンタイル：0.01(Thermodynamics)Investigation of the primary containment vessel inside the Fukushima Daiichi Nuclear Power Station showed that a significant amount of the molten corium reached the bottom of the pedestal region. The molten corium and concrete likely caused a complex interaction called Molten Corium Concrete Interaction. The solidification hysteresis of these ex-vessel debris significantly influences its properties. We performed a thermodynamic analysis using the TAF-ID database to infer the solidification path of U-Zr-Al-Ca-Si-O molten corium, which was chosen for a prototypic system of ex-vessel debris. The solidification path for the CaO-rich sim-corium showed that (i) melting as a single liquid phase above 2430 K, (ii) selective solidification of the oxide-rich corium mainly consisted of fuel materials, and (iii) solidification of the remaining materials as a silicate matrix. In contrast, the solidification path for the SiO
-rich corium indicated that (i) formation of liquid miscibility gap above 2200 K between U-rich and Zr-rich oxidic melts, (ii) individual precipitation of solid phases in each liquid phase.
Maurer, C.*; Galmarini, S.*; Solazzo, E.*; Ku
mierczyk-Michulec, J.*; Bar, J.*; Kalinowski, M.*; Schoeppner, M.*; Bourgouin, P.*; Crawford, A.*; Stein, A.*; et al.
Journal of Environmental Radioactivity, 255, p.106968_1 - 106968_27, 2022/12
被引用回数：2 パーセンタイル：14.8(Environmental Sciences)2015, 2016年のモデル比較演習を経て、2019年に包括的なXe-133大気輸送モデル比較試験を企画した。欧米の医療用RI製造施設であるIREやCNLからの排出の影響が大きいヨーロッパと北米にある4つのCTBT国際モニタリングシステム局を対象とし、約30の参加モデルの結果の比較とアンサンブルを実施した。第2回ATMチャレンジの教訓により、参加者は事務局の指定する条件に基づいて計算を実施した。その結果、IREとCNLからの正確な日別スタック排出量を使用しても、拡散過程における誤差、残存排出源の適切な特性化、長いIMSサンプリング時間(12
24時間)のデメリットと相殺され、平均すればスコアの改善が見られないことが確認された。一方、任意のモデル計算結果を用いたアンサンブルを実施したところ、今回対象とした4つの観測所でのXe-133バックグラウンドを十分に予測できることが確認できた。有効なアンサンブルのサイズは5以下であった。
Falyouna, O.*; Maamoun, I.; Ghosh, S.*; Malloum, A.*; Othmani, A.*; Eljamal, O.*; Amen, T. W. M.*; Oroke, A.*; Bornman, C.*; Ahmadi, S.*; et al.
Journal of Molecular Liquids, 368, Part B, p.120726_1 - 120726_25, 2022/12
被引用回数：5 パーセンタイル：38.46(Chemistry, Physical)Despite the carcinogenic and other adverse health effects ofchloramphenicol (CAP), it is frequently detected in different water sources (e.g., groundwater, surface water, wastewater effluents, etc.) due to ongoing, illegal, and abusive application of CAP in veterinary medicine. Although extensive research has been carried out to develop effective treatment technologies to remove the persistent CAP from aqueous mediums, yet there is no critical review of these studies to the best of our reach This review will be the first in the literature to comprehensively summarize the state-of-the-art treatment techniques for CAP removal from water. We report the removal of CAP by adsorption, biodegradation, nanoscale zerovalent iron technology (nZVI), and advanced oxidation processes (AOPs). The result shows that carbon-based adsorbents have more q
equal 892.86 mg/g for Porous carbon material from 
. The Langmuir- Freundlich isotherm and pseudo-second order kinetics model were reported to best describe the isotherm and kinetic model respectively. Removing the CAP via biodegradation would achieve the advantages of low operating costs, and environmental friendliness. The process of AOPs among the various treatment options can be a promising method for CAP degradation in water. This review comprehensively summarizes the state-of-the-art treatment techniques for CAP removal from water. Particularly, serving as an inclusive reference for future researchers to easily define the research gabs in the literature and plan for their future work in developing novel treatment methods to decontaminate CA-contaminated waters.
BaCo(PO)Sheng, J.*; Wang, L.*; Candini, A.*; Jiang, W.*; Huang, L.*; Xi, B.*; Zhao, J.*; Ge, H.*; Zhao, N.*; Fu, Y.*; et al.
Proceedings of the National Academy of Sciences of the United States of America, 119(51), p.e2211193119_1 - e2211193119_9, 2022/12
被引用回数：3 パーセンタイル：28(Multidisciplinary Sciences)Although considerable progress has been made in the theoretical understanding of the low-dimensional frustrated quantum magnets, experimental realizations of a well-established scaling analysis are still scarce. This is particularly true for the two-dimensional antiferromagnetic triangular lattices. Owing to the small exchange strength, the newly discovered compound NaBaCo(PO) provides a rare opportunity for clarifying the quantum criticality in an ideal triangular lattice with quantum spin S=1/2. In addition to the establishment of the complete phase diagrams, the spin Hamiltonian with a negligible interplane interaction has been determined through the spin wave dispersion in the polarized state, which is consistent with the observation of a two-dimensional quantum critical point with the Bose-Einstein condensation of diluted free bosons.
Sr and 
Cs by AMS本多 真紀; Martschini, M.*; Wieser, A.*; Marchhart, O.*; Lachner, J.*; Priller, A.*; Steier, P.*; Golser, R.*; 坂口 綾*
JAEA-Conf 2022-001, p.85 - 90, 2022/11
加速器質量分析(AMS)は、原子核実験で主に利用させれてきたタンデム加速器に質量分析を組み合わせた分析法である。AMSの測定対象は半減期が10
-10
年の放射性核種である。この程度の半減期の放射性核種に対しては、その放射能を測定するよりも、その質量を測定する手法の方が10-10
倍の感度で測定可能である。この特徴を利用してAMSは地球惑星科学、原子力分野等の研究に幅広く適応されている。様々な研究の中でもWallner et al. (2021, 2016)は地球惑星科学の分野で優れた成果を得ている。彼らは環境試料に含まれる
Feと
Puの超高感度分析に成功した。これらは天体内で起こる中性子の連続捕獲(r-process)によって生成される放射性核種である。この他に、発表者らの最新の研究ではレーザーによる同重体分離とAMSとを組み合わせた新AMSシステム(ウィーン大学VERA)による環境試料中のSrとCsの超高感度分析に成功した。環境中のSr測定手法としては娘核種Yのミルキングによる
線測定が依然主力であるが、本成果によってAMSが実用的な新規分析法となることが示された。本発表ではSrとCsを中心に超高感度分析の技術開発の現状を報告する。
Hamdani, A.; 安部 諭; 石垣 将宏; 柴本 泰照; 与能本 泰介
Progress in Nuclear Energy, 153, p.104415_1 - 104415_16, 2022/11
被引用回数：3 パーセンタイル：68.71(Nuclear Science & Technology)This paper describes the computational fluid dynamics (CFD) analysis and validation works from the previous experimental study on the natural convection driven by outer surface cooling in the presence of density stratification consisting of air and helium (as a mimic gas of hydrogen). The experiment was conducted in the Containment InteGral effects Measurement Apparatus (CIGMA) facility at Japan Atomic Energy Agency (JAEA). The numerical simulation was carried out to analyze the detailed effect of the cooling region on the erosion of the helium stratification layer. The temporal and spatial evolution of the helium concentration and the gas temperature inside the containment vessel was predicted and validated against the experimental data. In addition, two stratification behaviors that depend on the cooling location were presented and discussed. The CFD simulation confirmed that an upper head cooling caused two counter-rotating vortexes in the helium-rich zone. Meanwhile, the upper half body cooling caused two counter-rotating vortexes in the helium-poor zone. These findings are important to understand the mechanism of the density stratification process driven by natural convection in the containment vessel.
中村 秀夫; Bentaib, A.*; Herranz, L. E.*; Ruyer, P.*; Mascari, F.*; Jacquemain, D.*; Adorni, M.*
Proceedings of International Conference on Topical Issues in Nuclear Installation Safety; Strengthening Safety of Evolutionary and Innovative Reactor Designs (TIC 2022) (Internet), 10 Pages, 2022/10
The WGAMA activity achievements have been published as technical reports, becoming reference materials to discuss innovative methods, materials and technologies in the fields of thermal-hydraulics, computational fluid dynamics (CFD) and severe accidents (SAs). The International Standard Problems (ISPs) and Benchmarks of computer codes have been supported by a huge amount of the databases for the code validation necessary for the reactor safety assessment with accuracy. The paper aims to review and summarize the recent WGAMA outcomes with focus on new advanced reactor applications including small modular reactors (SMRs). Particularly, discussed are applicability of major outcomes in the relevant subjects of passive system, modelling innovation in CFD, severe accident management (SAM) countermeasures, advanced measurement methods and instrumentation, and modelling robustness of safety analysis codes. Although large portions of the outcomes are considered applicable, design-specific subjects may need careful considerations when applied. The WGAMA efforts, experiences and achievements for the safety assessment of operating nuclear power plants including SA will be of great help for the continuous safety improvements required for the advanced reactors including SMRs.
and its impact on photoproduction of light hyperonsKhemchandani, K. P.*; Mart
nez Torres, A.*; Kim, S.-H.*; Nam, S.-I.*; 保坂 淳
Acta Physica Polonica A, 142(3), p.329 - 336, 2022/09
被引用回数：0 パーセンタイル：0(Physics, Multidisciplinary)In this work, we outline the findings of our recent study of the properties of and its consequential impacts on the cross-sections of the photoproduction of 
(1405). Further, we discuss the possibility of the existence of an isovector state with a mass similar to (1405), which we refer to as 
(1400). With the idea of motivating experimental investigations of (1400), we have studied its photo-production process and determined the respective cross-sections and polarization observables. We have studied also the coupling of to 
(1400) and found that it gives an important contribution to the cross-sections near the threshold. In the process, we have determined the branching ratios of the decay of to the final states involving (1405) and (1400) to be in the range of 6-7 MeV. Our findings can motivate the consideration of alternative processes in partial wave analyses of experimental data when studying the properties of .
Sr analysis of environmental samples by ion-laser interaction mass spectrometry本多 真紀; Martschini, M.*; Marchhart, O.*; Priller, A.*; Steier, P.*; Golser, R.*; 佐藤 哲也; 塚田 和明; 坂口 綾*
Analytical Methods, 14(28), p.2732 - 2738, 2022/07
被引用回数：2 パーセンタイル：45.92(Chemistry, Analytical)環境放射線学の発展に資するために加速器質量分析装置(AMS)による高感度Sr分析法を開発した。AMSの利点は、Sr/
Srの原子比が10
の様々な環境試料を簡単な化学分離で分析できることである。本研究ではSr濃度が既知の3種類のIAEA試料(コケ土、動物の骨、シリアの土壌:各1g)を分析し、化学分離とAMS測定の妥当性を評価した。Srの測定は、優れた同重体分離性能を有するウィーン大学のイオンレーザーインターアクション質量分析装置(ILIAMS)と組み合わせたAMSシステムで実施した。SrのAMSにおけるZrの同重体干渉は、まず化学分離によって除去された。Sr樹脂と陰イオン交換樹脂を用いた2段階のカラムクロマトグラフィーにおけるZrの分離係数は10であった。試料中に残存するZrはILIAMSによって効率的に除去された。この簡単な化学分離で一般的な線検出よりも低い検出限界
0.1mBqを達成した。Sr濃度に関して本研究のAMS測定値とIAEAの公称値が一致したことから、AMSによる新規の高感度Sr分析は土壌や骨の高マトリクス試料に対しても信頼できることを示した。
0 transition strength for 
Se using the SPICE spectrometerSmallcombe, J.; Garnsworthy, A. B.*; Korten, W.*; Singh, P.*; Ali, F. A.*; Andreoiu, C.*; Ansari, S.*; Ball, G. C.*; Barton, C. J.*; Bhattacharjee, S. S.*; et al.
Physical Review C, 106(1), p.014312_1 - 014312_9, 2022/07
被引用回数：3 パーセンタイル：66.85(Physics, Nuclear)The selenium isotopes lie at the heart of a tumultuous region of the nuclear chart where shape coexistence effects grapple with neutron-proton pairing correlations, triaxiality, and the impending proton dripline. In this work a study of Se by internal conversion electron and 
-ray spectroscopy was undertaken with the SPICE and TIGRESS arrays. New measurements of the branching ratio and lifetime of the 
state were performed yielding a determination of 
milliunits. Two state mixing calculations were performed that highlighted the importance of interpretation of such 
strength values in the context of shape-coexistence.
Walter, H.*; Colonna, M.*; Cozma, D.*; Danielewicz, P.*; Ko, C. M.*; Kumar, R.*; 小野 章*; Tsang, M. Y. B*; Xu, J.*; Zhang, Y.-X.*; et al.
Progress in Particle and Nuclear Physics, 125, p.103962_1 - 103962_90, 2022/07
被引用回数：48 パーセンタイル：96.94(Physics, Nuclear)原子核-原子核衝突や原子核の状態方程式の研究において、反応計算モデルは重要なツールとなり、世界中で開発が進んでいる。本論文は、原子力機構のJQMD-2.0を含め、現在開発中の複数のコード開発者の協力により、これらコードを同じ条件で比較することで共通点や差異を明らかにしたプロジェクトTransport Model Evaluation Project (TMEP)を総括したものである。参加したコードはBoltzmann-Uehling-Uhlenbeck(BUU)法に基づく13のコードと、Quantum Molecular Dynamics (QMD)法に基づく12のコードであった。プロジェクトでは、Au原子核同士を衝突させてその終状態を観測する現実的な計算や、一辺が640nmの箱に核子を詰めて時間発展させる仮想的な計算を行った。その結果、BUU法コードとQMD法コードは計算原理が異なるため、計算の設定に関係なく系統的な差異が生じることが明らかになった。その一方で、同じ方法を採用するコード間の比較では、時間発展を細かく計算することでコード間の差は埋まっていき、一定の収束値を持つことが示された。この結果は今後開発される同分野のコードのベンチマークデータとして有用なものであるだけでなく、原子核基礎物理学の実験や理論研究の標準的な指針としても役に立つことが期待される。
石垣 将宏*; 安部 諭; Hamdani, A.; 廣瀬 意育
Annals of Nuclear Energy, 168, p.108867_1 - 108867_20, 2022/04
被引用回数：4 パーセンタイル：68.71(Nuclear Science & Technology)It is essential to improve computational fluid dynamics (CFD) analysis accuracy to estimate thermal flow in a containment vessel during a severe accident. Previous studies pointed out the importance of the influence of initial and boundary conditions on the CFD analysis. The purpose of this study is to evaluate the influence of initial and boundary conditions by numerical analysis of natural convection experiments in a large containment vessel test facility CIGMA(Containment InteGral effects Measurement Apparatus). A density stratification layer was initially formed in the vessel using helium and air, and external cooling of the vessel surface-induced natural convection. In this study, we carried out numerical simulations of the density stratification erosion driven by the natural convection using the RANS (Reynolds averaged Navier-Stokes) model. As a result, the temperature boundary condition of the small internal structure in the vessel had a significant influence on the fluid temperature distribution in the vessel. The erosion velocity of the density stratification layer changed depending on the initial gas concentration distribution. Then, appropriate settings of the temperature and gas concentration conditions are necessary for accurate analysis.
Quaini, A.*; Goss, S.*; Payot, F.*; Suteau, C.*; Delacroix, J.*; Saas, L.*; Gubernatis, P.*; Martin-Lopez, E.*; 山野 秀将; 高井 俊秀; et al.
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 10 Pages, 2022/04
CEAと原子力機構は、現在の実施体制の下で新しいサブタスク、炉心混合物質における相互作用の動力学、炉心混合物質の物性、UO-Fe-BC系の高温熱力学データ、BC-SS速度論およびBC-SS共晶材料の再配置(凍結)に関する実験的研究、SIMMERコードシステムのBC/SS共晶および動力学モデル、混合物の液相化速度をモデル化するための方法論を定義した。この論文は、以前の実施協定の下での日仏協力で得られた主要な研究開発結果と、現在の協定の下での実験的および分析的ロードマップについて説明する。
久保 重信; Payot, F.*; 山野 秀将; Bertrand, F.*; Bachrata, A.*; Saas, L.*; Journeau, C.*; Gosse, S.*; Quaini, A.*; 柴田 明裕*; et al.
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 8 Pages, 2022/04
The paper presents major outcomes of the France-Japan ASTRID collaboration and the work program from 2020 to 2024 in the field of severe accident study. In the ASTRID collaboration, severe accident sequences were summarized based on the various safety analyses for the important accident phases, which contributed to strengthen the confidence in the ASTRID severe accident progression for a robust safety demonstration and identification of R and D programs of common interest. Collaborative analysis has been conducted to evaluate ASTRID mitigation device efficiency for mitigation of power excursions, material relocation, debris bed and molten pool behavior on the core catcher. The methodology for mechanical consequence assessment was also developed. In order to support the reactor studies, experimental studies have been planned and conducted regarding the reaction of core material mixtures, in-pile experiments for the fuel pin failure and material relocation through a steel duct structure, and out-of-pile experiments for the fuel coolant interaction (FCI) in the sodium pool. Severe accident analysis tool SIMMER-V with new simulation capabilities and SEASON platform have also been developed. Based on these successful achievements, several tasks to study the large fields of the severe accident domain, which include development of severe accident analysis methodologies and synthesis of SA sequences and consequences, thermodynamics, kinetic and thermo-physical studies of core material mixture, development and validation of SIMMER-V, experimental programs on the molten core material relocation and FCI. After defining the technical contents and implementation plans, the five years study programs have been started.
