検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年
検索結果: 175 件中 1件目~20件目を表示

発表形式

Initialising ...

選択項目を絞り込む

掲載資料名

Initialising ...

発表会議名

Initialising ...

筆頭著者名

Initialising ...

キーワード

Initialising ...

使用言語

Initialising ...

発行年

Initialising ...

開催年

Initialising ...

選択した検索結果をダウンロード

論文

Case study on sampling techniques using machine learning and simplified physical model for simulation-based dynamic probabilistic risk assessment

久保 光太郎; Zheng, X.; 石川 淳; 杉山 智之; Jang, S.*; 高田 孝*; 山口 彰*

Proceedings of Asian Symposium on Risk Assessment and Management 2020 (ASRAM 2020) (Internet), 11 Pages, 2020/11

動的確率論的リスク評価(PRA)は、従来のPRAよりも現実的で詳細な解析を可能とする。しかし、これらの改善とトレードオフの関係にあるのは、多数の熱水力解析を行うことに伴う膨大な計算コストである。本研究では、機械学習に基づいて、熱水力解析を省略することでこの計算コストを削減することを目指した。機械学習には、サポートベクターマシンを選択し、その構築には高忠実度・高コストの詳細モデルと、低忠実度・低コストの簡易モデルを用いた。その結果、今回仮定した条件においては、精度を大幅に低下させることなく計算コストを約80%削減することができた。

論文

The Analysis for Ex-Vessel debris coolability of BWR

松本 俊慶; 岩澤 譲; 安島 航平*; 杉山 智之

Proceedings of Asian Symposium on Risk Assessment and Management 2020 (ASRAM 2020) (Internet), 10 Pages, 2020/11

本研究では、事前注水した格納容器内デブリの冷却確率を評価した。まず、落下溶融物条件を求めるため、シビアアクシデント解析コードMELCORによる不確かさ解析を行った。この解析では炉心の溶融・移行過程に関連する5つの不確かさパラメータを選択し、仮定された確率分布を用いて、ラテン超方格法(LHS)により入力パラメータセットを生成した。これを用いたMELCORによる多ケース解析の結果から落下溶融物条件を抽出した。次に、MELCOR解析結果をもとに、パラメータの確率分布を決定し、LHSにより生成した59個のパラメータセットを用いてJASMINEコードによる水中の溶融物挙動の解析を行った。水位の条件は0.5m, 1.0m及び2.0mとした。広がり半径とデブリ質量の解析結果からデブリの堆積高さを求め、判定基準と比較することで冷却の成否判定を行った。以上の一連の解析の結果、デブリ冷却の成功確率を求めた。また、MELCOR及びJASMINEを組み合わせた冷却性解析の課題について論じた。

論文

A Comparative study of sampling techniques for dynamic probabilistic risk assessment of nuclear power plants

久保 光太郎; Zheng, X.; 田中 洋一; 玉置 等史; 杉山 智之; Jang, S.*; 高田 孝*; 山口 彰*

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.308 - 315, 2020/10

動的確率論的リスク評価(PRA)PRAは従来のPRA手法の現実性と網羅性を向上させる手法の一つである、しかしながら、それらの向上と引き換えに膨大な計算コストが発生する。本稿では、複数のサンプリング手法を簡易的な事故シーケンスに対する動的PRAに対して適用した。具体的には、モンテカルロ法,ラテン超方格法,格子点サンプリング及び準モンテカルロ法を比較した。その結果、今回の検討の範囲においては、準モンテカルロ法が最も効率的であった。

論文

Consistent robin boundary enforcement of particle method for heat transfer problem with arbitrary geometry

Wang, Z.; Duan, G.*; 松永 拓也*; 杉山 智之

International Journal of Heat and Mass Transfer, 157, p.119919_1 - 119919_20, 2020/08

 被引用回数:1 パーセンタイル:28.34(Thermodynamics)

Enforcing accurate and consistent boundary conditions is a difficult issue for particle methods, due to the lack of information outside boundaries. Recently, consistent Neumann boundary condition enforcement is developed for the least squares moving particle semi-implicit method (LSMPS). However, the Robin boundary cannot be straightforwardly considered by that method because no computational variables are defined on the wall boundary. In this paper, a consistent Robin boundary enforcement for heat transfer problem is proposed. Based on the Taylor series expansion, the Robin boundary condition for temperature is converted to the fitting function of internal rather than boundary particles and incorporated into least squares approach for discretization schemes. Arbitrary geometries can be easily treated due to the use of polygons for wall boundary. A convergence study was firstly carried out to verify the consistency. Then, numerical tests of 1-D and 2-D heat conduction problems subjected to mixed boundary conditions were performed for verification, and good agreements with theoretical solutions were observed. Natural convection problems with different boundary conditions in an annulus were carried out for further validations of heat-fluid coupling. Excellent agreements between the present and literature results were demonstrated.

論文

Development of a multiphase particle method for melt-jet breakup behavior of molten core in severe accident

Wang, Z.; 岩澤 譲; 杉山 智之

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 12 Pages, 2020/08

In a hypothetical severe accident in a light water reactor (LWR) nuclear power plant, there is a possibility that molten core released from the reactor vessel gets in contact with water in the containment vessel. In this so-called fuel-coolant interactions (FCIs) process, the melt jet will breakup into fragments, which is one of the important factors for a steam explosion, as a potential threat to the integrity of the containment vessel. In order to investigate the melt-jet breakup with solidification processes, a multiphase particle method is developed in this study. Benefiting from its Lagrangian description and meshless framework, the large deformed interfaces could be directly and easily captured by the particle motions. A simple transient heat conduction test is firstly carried out. Two important multiphase instabilities, namely the Rayleigh-Taylor instability and the Kelvin-Helmholtz instability, are studied since they play important roles during the melt-jet breakup. After that, a bubble rising benchmark is performed to show the feasibility of modelling for deformation and collapse. The results achieved so far indicates that the developed particle method is capable to analyze the melt-jet breakup with solidification processes.

論文

Computational study on the spherical laminar flame speed of hydrogen-air mixtures

Trianti, N.; 茂木 孝介; 杉山 智之; 丸山 結

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 9 Pages, 2020/08

The computational fluid dynamics (CFD) have been developed to analyze the correlation equation for laminar flame speed of hydrogen-air mixtures. This analysis was carried out on the combustion of hydrogen-air mixtures performed at the spherical bomb experiment facility consists of a spherical vessel equipped (563 mm internal diameter). The facility has been designed and built at CNRS-ICARE laboratory. The simulation was carried out using the reactingFoam solver, one of a transient chemical reaction solver in OpenFOAM 5.0. The LaunderSharmaKE model was applied for turbulent flow. The interaction of the chemical reaction with the turbulent flow was taken into account using PaSR (Partial Stirred Reactor) model with 19 elementary reactions for the hydrogen combustion. The initial condition of spherical flame analysis was set so as to be consistent with those of the experiment. The position of the flame front was detected by the steep drop of hydrogen mass fraction in the spherical radii, and the flame propagation velocity was estimated from the time-position relationship. The analysis result showed the characteristic of spherical flame acceleration was qualitatively reproduced even though it has a discrepancy with the experiment. After validating the calculation of spherical experiments, a laminar burning velocity correlation is presented using the same boundary conditions with the variation of hydrogen concentration, temperature, and pressure. The calculation of laminar flame speed of hydrogen-air mixtures by reactingFoam use reference temperature T$$_{rm ref}$$ = 293 K and reference pressure P$$_{rm ref}$$ = 1 atm with validated in the range of hydrogen concentration 6-20%; range of temperature 293-493 K; and range of pressure 1-3 atm.

論文

Experimental and analytical investigation of formation and cooling phenomena in high temperature debris bed

堀田 亮年*; 秋葉 美幸*; 森田 彰伸*; Konovalenko, A.*; Vilanueva, W.*; Bechta, S.*; Komlev, A.*; Thakre, S.*; Hoseyni, S. M.*; Sk$"o$ld, P.*; et al.

Journal of Nuclear Science and Technology, 57(4), p.353 - 369, 2020/04

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)

Key phenomena in the cooling states of debris beds under wet cavity conditions were classified into several groups based on the complicated geometry, nonhomogeneous porosity and volumetric heat of debris beds. These configurations may change due to the molten jet breakup, droplet agglomeration, anisotropic melt spreading, two-phase flow in a debris bed, particle self-leveling and penetration of molten metals into a particle bed. The modular code system THERMOS was designed for evaluating the cooling states of underwater debris beds. Three additional tests, DEFOR-A, PULiMS and REMCOD were employed to validate implemented models. This paper summarizes the entire test plan and representative data trends prior to starting individual data analyses and validations of specific models that are planned to be performed in the later phases. It also tries to report research questions to be answered in future works, such as various scales of melt-coolant interactions observed in the PULiMS tests.

論文

Thresholds for failure of high-burnup LWR fuels by pellet cladding mechanical interaction under reactivity-initiated accident conditions

宇田川 豊; 杉山 智之; 天谷 政樹

Journal of Nuclear Science and Technology, 56(12), p.1063 - 1072, 2019/12

 被引用回数:2 パーセンタイル:34.3(Nuclear Science & Technology)

反応度事故時のペレット・被覆管相互作用により生じる軽水炉燃料の破損に関して、我が国の規制基準改訂の検討に資するため、原子炉安全性研究炉NSRRを用いて得られた近年の研究成果を総括する。これに基づき、現行基準の妥当性及び現行基準に代わりうる新たな判断基準としての燃料破損しきい値とその考え方について議論する。

論文

CFD analysis of hydrogen flame acceleration with burning velocity models

茂木 孝介; Trianti, N.; 松本 俊慶; 杉山 智之; 丸山 結

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.4324 - 4335, 2019/08

Hydrogen managements under severe accidents are one of the most crucial problems and have attracted a great deal of attention after the occurrence of hydrogen explosions in the accident at Fukushima Daiichi Nuclear Power Plant in March 2011. The primary purpose of our research is improvements in computational fluid dynamics techniques to simulate hydrogen combustion. Our target of analysis is ENACCEF2 hydrogen combustion benchmark test conducted in the framework of ETOSON-MITHYGENE project. Flame acceleration experiments of hydrogen premixed turbulent combustions were simulated by the Turbulent Flame Closure (TFC) model. We implemented several laminar flame speed correlations and turbulent flame speed models on XiFoam solver of OpenFOAM and compared the results to investigate the applicability of these correlation and model equations. We found that all the laminar flame speed correlations could predict qualitative behavior of the flame acceleration, but Ravi & Petersen laminar flame speed correlation that is originally implemented in OpenFOAM underestimated the maximum flame speed for the lean hydrogen concentration. Zimont model and G$"u$lder model of the turbulent flame speed could reasonably simulate the flame acceleration behavior and maximum pressure peaks. The flame velocities calculated with G$"u$lder model tend to be faster than that calculated with Zimont model.

論文

Analysis for the accident at unit 1 of the Fukushima Daiichi NPS with THALES2/KICHE code in BSAF2 project

玉置 等史; 石川 淳; 杉山 智之; 丸山 結

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.72 - 82, 2019/08

原子力機構では、BSAF2計画に参加し、THALES2/KICHEコードを用いた福島第一原子力発電所の事故解析結果を提供した。THALES2/KICHEコードの重要な特徴の一つとして、液相における速度論に基づくヨウ素化学をモデル化している。本報告では、BSAF2計画における共通の境界条件や仮定に加え、格納容器の破損として、ベント弁が完全に閉まらなかったために引き起こされるベントラインからの継続的な漏洩をモデル化した1号機の3週間にわたる解析結果について紹介する。本仮定に基づく解析では、原子炉冷却系や格納容器の圧力履歴を再現できており、解析期間の3週間で環境に放出されたヨウ素及びセシウムの初期インベントリに対する割合は、各々約6%及び約1%であった。

論文

Analysis for the accident at unit 2 of the Fukushima Daiichi NPS with THALES2/KICHE code in BSAF2 project

玉置 等史; 石川 淳; 杉山 智之; 丸山 結

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.100 - 111, 2019/08

JAEAでは、BSAF2計画に参加し、THALES2/KICHEコードを用いた福島第一原子力発電所の事故解析結果を提供した。THALES2/KICHEコードの重要な特徴の一つとして、液相における速度論に基づくヨウ素化学をモデル化している。本報告では、BSAF2計画における共通の境界条件や仮定に基づいた3週間にわたる2号機の解析結果、特にBSAF2計画では、2号機の事故進展に関し、3月14日の20時から15日2時の間に観測された3つの圧力容器内圧力ピークの生じた理由に着目しており、この時期の事故進展挙動を含め紹介する。また、本解析では、圧力抑制室の下部に破損を仮定し、水の漏洩を含め、格納容器圧力挙動を再現した。解析期間の3週間で環境に放出されたヨウ素及びセシウムの初期インベントリに対する割合は、各々約3%及び約0.1%であった。

論文

Analysis for the accident at Unit 3 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 project

石川 淳; 玉置 等史; 杉山 智之; 丸山 結

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.536 - 547, 2019/08

Japan Atomic Energy Agency is pursuing the development and application of the integrated severe accident analysis code, THALES2/KICHE for analysis of severe accident progression and source term. The accident at the Fukushima Daiichi Nuclear Power Station (NPS) from units 1 to 3 were analyzed using THALES2/KICHE code for better understanding of the accident in the OECD/NEA BSAF2 project. This paper describes three week analysis for the accident at unit 3. The leakage through the drywell head flange and an equipment hutch was assumed in order to reproduce the tendency of drywell pressure history in addition to the intermittent activation of the containment vessel venting system via the suppression chamber. As for the source term analysis, the dominant chemical forms for cesium and iodine were assumed to be cesium iodine (CsI) and cesium molibdate (Cs$$_{2}$$MoO$$_{4}$$) based on the insights of the PHEBUS/FP experiments. The iodine chemical reaction kinetics in the containment aqueous phase, which were associated with the production of molecular iodine and organic iodide, were taken into consideration in the present analysis. The released iodine and cesium within three weeks after the earthquake were predicted to be approximately 3% and 6% of the initial inventory, respectively.

論文

Outline of the OECD/NEA/ARC-F Project

中塚 亨; 前田 敏克; 杉山 智之; 丸山 結

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.1650 - 1656, 2019/08

経済協力開発機構原子力機関(OECD/NEA)は、「福島第一原子力発電所の原子炉建屋および格納容器内情報の分析(ARC-F)」プロジェクトを新たに開始した。本プロジェクトは、OECD/NEAで先行して実施された東京電力ホールディングス福島第一原子力発電所事故ベンチマーク解析(BSAF)プロジェクトの後継としての役割を担う。プロジェクトは、次の3つのタスクからなる。(1)事故進展解析及び核分裂生成物の移行と拡散やソースタームに関する解析の高度化(BSAF及びBSAF2プロジェクトのフォローアップ)、(2)得られたデータ・情報の集約管理、(3)将来の長期プロジェクトの検討。プロジェクトの運営は、原子力機構が行う。実施期間は、2019年1月から2021年12月までの3年間で、最終報告書は2022年に発行予定である。

論文

Formation of agglomerated debris in jet-breakup experiment using metallic melts

岩澤 譲; 杉山 智之; 丸山 結; 金子 暁子*; 阿部 豊*

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 6 Pages, 2019/05

For evaluation of the debris coolability, agglomeration, which is merging of melt particles with the others and formation of massive debris, is critical in the severe accidents in light water reactors. We carried out small-scale experiments of agglomerated debris formation using metallic melt to establish a data base for modelling and validation. Molten metal of low melting point was ejected into a test section filled with water though a nozzle. A high-speed video camera recorded images of settlement of the melt particles generated form a melt jet onto a plate located in the test section. After the melt injection, we collected the debris and investigated detailed shapes of the debris. Based on the results, we assessed the feasibility of the experiments of agglomeration using the metallic melt.

論文

Analysis of transport behaviors of cesium and iodine in VERDON-2 experiment for chemical model validation

塩津 弘之; 伊藤 裕人*; 石川 淳; 杉山 智之; 丸山 結

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 6 Pages, 2018/11

The VERDON-2 experiment for FPs transport in steam environment was analyzed with the mechanistic FPs transport code incorporating thermodynamic chemical equilibrium model in order to assess its predictive capability for transport behavior of key FPs, especially for highly volatile FPs such as Cs and I. The present analysis reproduced well the Cs deposition profile obtained from the experiment, which revealed that Cs was transported as CsOH in early phase of FP release from fuel, and then formed Cs$$_{2}$$MoO$$_{4}$$ after increasing Mo release. On the other hand, the deposition peak of I was predicted to appear at 720 K, which was significantly higher than the experimental result at 600 K. This discrepancy was potentially caused by the following two points: lack of the other stable species in thermodynamics database for thermodynamic chemical equilibrium model, or failure of chemical equilibrium assumption for iodide species.

論文

Computational fluid dynamics analysis for hydrogen deflagration tests at ENACCEF2 facility

Trianti, N.; 佐藤 允俊*; 杉山 智之; 丸山 結

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 7 Pages, 2018/11

Simulation techniques have been developed to analyze the deflagration behavior of hydrogen generated during a hypothetical severe accident in nuclear power plants. The CFD analysis was carried out on the hydrogen deflagration experiment performed at the ENACCEF2 facility composed mainly of a vertical cylindrical tube filled with hydrogen-air mixture and nine annular obstacles were placed in the lower part of the tube. The simulation was carried out by the reactingFoam solver of OpenFOAM 3.0, an open source software for the CFD analysis. The RNG (Renormalization group) k-$$varepsilon$$ model was applied for turbulent flow. The interaction of the chemical reaction with the turbulent flow was considered using PaSR (Partial Stirred Reactor) model with 19 elementary reactions for the hydrogen combustion. The analysis result showed the characteristic of flame acceleration by the obstacle region was qualitatively reproduced even though has discrepancy with the experiment.

報告書

CHEMKEq; 化学平衡論及び反応速度論の部分混合モデルに基づく化学組成評価コード(受託研究)

伊藤 裕人*; 塩津 弘之; 田中 洋一*; 西原 慧径*; 杉山 智之; 丸山 結

JAEA-Data/Code 2018-012, 42 Pages, 2018/10

JAEA-Data-Code-2018-012.pdf:4.93MB

原子力施設事故時において施設内を移行する核分裂生成物(FP)の化学組成は、比較的遅い反応の影響を受けることにより化学平衡を仮定して評価した組成とは異なる場合が想定される。そのため、反応速度を考慮した化学組成評価が求められる。一方で、原子力施設事故時の複雑な反応に関する反応速度の知見は現状では限られており、実機解析に適用できるデータベースの構築に至っていない。そこで、FP化学組成評価における反応速度による不確かさの低減のため、化学平衡論及び反応速度論の部分混合モデルに基づく化学組成評価コードCHEMKEqを開発した。このモデルは、系全体の質量保存則の下、前駆平衡と見なせる化学種を化学平衡論モデルにより評価し、その後の比較的遅い反応を反応速度論モデルにより解くものである。さらにCHEMKEqは、本混合モデルに加え一般的な化学平衡論モデル及び反応速度論モデルが使用可能であり、かつ、それらモデル計算に必要なデータベースを外部ファイル形式とすることで汎用性の高い化学組成評価コードとなっている。本報は、CHEMKEqコードの使用手引書であり、モデル, 解法, コードの構成とその計算例を記す。また付録には、CHEMKEqコードを使用する上で必要な情報をまとめる。

論文

Sensitivity analysis of source term in the accident of Fukushima Dai-ichi Nuclear Power Station Unit 1 using THALES2/KICHE

玉置 等史; 石川 淳; 杉山 智之; 丸山 結

Proceedings of Asian Symposium on Risk Assessment and Management 2018 (ASRAM 2018) (USB Flash Drive), 6 Pages, 2018/10

福島第一原子力発電所で生じた事故では、津波を原因とした電源喪失により、炉心損傷及び格納容器の損傷に至り核分裂性物質が環境に放出された。事故時に計測されたデータ及び事故進展解析、また、事故を起こしたプラントの建屋及び格納容器内部の調査により、事故進展の理解は進んでいる。一方でプラント内事故進展解析と放出された放射性物質の拡散解析の連携解析を行っている例は多くはない。原子力機構では、シビアアクシデント解析と確率論的事故影響評価との連携解析を計画している。この連携解析では、多くの不確かな要因による幅広い不確かさ幅が予想される。この連携解析を効率的に行うため、事故を起こしたプラントのうち、はじめに環境へのFP放出があった1号機を対象に、格納容器の破損箇所及び漏えい面積について、原子力機構で開発しているTHALES2/KICHEを用いた感度解析を行った。想定する格納容器の破損個所は、ヘッドフランジ、ペネトレーションシール及び真空破壊弁配管とした。これに加え、ベント弁の一部開を想定した解析結果も含め、報告する。

論文

Evaluation of chemical speciation of iodine and cesium considering fission product chemistry in reactor coolant system

石川 淳; Zheng, X.; 塩津 弘之; 杉山 智之; 丸山 結

Proceedings of Asian Symposium on Risk Assessment and Management 2018 (ASRAM 2018) (USB Flash Drive), 6 Pages, 2018/10

Japan Atomic Energy Agency is pursuing the development and application of the methodologies on fission product (FP) chemistry for source term analysis by using integrated severe accident analysis code THALES2/KICHE. Generally, specific chemical forms of iodine and cesium such as cesium iodide (CsI) and cesium hydroxide (CsOH) were assumed in the source term analysis for light water reactors using an integrated severe accident analysis code. The accident at the Fukushima Dai-ichi Nuclear Power Station leads possible chemical effects of B$$_{4}$$C control materials and atmosphere on chemical speciation of iodine and cesium such as cesium metaborate (CsBO$$_{2}$$) and hydrogen iodide (HI). The difference of chemical speciation affects not only the FP behavior in the reactor coolant system (RCS) and transport to containment but also pH value of the suppression pool water in the containment. The pH value is one of the influential factors on the release of gaseous iodine (I$$_{2}$$ and organic iodine) from containment liquid phase. In the present study, the improvement of the THALES2/KICHE code in terms of FP chemistry in RCS was performed and applied to source term analysis for severe accidents at a boil water reactor with Mark-I containment vessel. This paper discusses the chemical speciation of iodine and cesium, and FP behavior and transport to containment.

論文

Severe accident scenario uncertainty analysis using the dynamic event tree method

Zheng, X.; 玉置 等史; 石川 淳; 杉山 智之; 丸山 結

Proceedings of 14th International Conference on Probabilistic Safety Assessment and Management (PSAM-14) (USB Flash Drive), 10 Pages, 2018/09

Several types of uncertainties exist during the simulation of a severe accident. These may result from incomplete knowledge about the plant systems, accident progression and oversimplified numerical models. Among them, parameter uncertainty can be treated via Monte-Carlo-sampling-based methods. To tackle the severe accident scenario uncertainty, we must resort to advanced dynamic probabilistic risk assessment (PRA) methods. In this paper, authors reviewed the previous dynamic PRA methods and tools, and then performed a preliminary scenario uncertainty analysis, by using an integrated SA code (THALES2) and a scenario generator (RAPID, risk assessment with plant interactive dynamics), both being developed at JAEA. THALES2 is a fast-running severe accident code for the simulation of severe accident progression and source term in light water reactors. Typical scenarios of station-blackout (SBO)-initiated accidents in boiling water reactors are generated and simulated. The dynamic event tree (DET) method is applied to consider the stochastic uncertainties during the scenario progression. Major groups of SBO sequences with the similar accident characteristics can be found. To provide a reference value for risk, a conditional core damage frequency is calculated accordingly. This is a preliminary analysis for severe accident scenario uncertainty quantification at JAEA, and further DPRA researches are in progress.

175 件中 1件目~20件目を表示