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論文

ETSON-SAMHYCO-NET benchmark on simulations of upward flame propagation experiment in representative hydrogen-air-steam mixtures of severe accidents containments atmosphere

Bentaib, A.*; Chaumeix, N.*; Nyrenstedt, G.*; Bleyer, A.*; Maas, L.*; Gastaldo, L.*; Kljenak, I.*; Dovizio, D.*; Kudriakov, S.*; Schramm, B.*; et al.

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 11 Pages, 2022/03

In case of a core melt-down accident in a light water nuclear reactor, hydrogen is produced during reactor core degradation and released into the reactor building. In case of failure of in-vessel corium retention, a large amount of carbon monoxide (CO) in addition to H$$_{2}$$ and other gases may be produced during molten core concrete interaction (MCCI). This subsequently creates a combustion hazard. A local ignition of the combustible mixture may generate standing flames or initially slow propagating flames. Depending on geometry, mixture composition and turbulence level, the flame can accelerate or be quenched after a certain distance. The pressure and temperature loads generated by the combustion process may threaten the integrity of the containment building and safety equipment. The evaluation of such loads requires validated codes which can be used with a high level of confidence. Currently, turbulence and steam effect on flame propagation mechanisms are not well reproduced by combustion models usually implemented in safety tools and further model enhancement and validation are still needed. For this purpose and at the initiative of the SAMHYCO-NET project consortium and of the European Technical Safety Organization Network (ETSON), a benchmark on hydrogen combustion was organized with the goal to identify the current level of the computational tools in the area of hydrogen combustion simulation under conditions typical for safety considerations in a Nuclear Power Plant (NPP). This benchmark is composed of four main steps with increasing difficulty starting from flame propagation in homogenous dry atmosphere and finishing with more representative conditions with (H$$_{2}$$/H$$_{2}$$O/O$$_{2}$$/N$$_{2}$$) stratified mixtures. In this paper, only experiments related to flame propagation in homogenous atmosphere are considered.

論文

ETSON-MITHYGENE benchmark on simulations of upward flame propagation experiment in the ENACCEF2 experimental facility

Bentaib, A.*; Chaumeix, N.*; Grosseuvres, R.*; Bleyer, A.*; Gastaldo, L.*; Maas, L.*; Jallais, S.*; Vyazmina, E.*; Kudriakov, S.*; Studer, E.*; et al.

Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) (USB Flash Drive), 11 Pages, 2018/10

In the framework of the French MITHYGENE project, the new highly instrumented ENACCEF2 facility was built at the Institut de Combustion Aerothermique Reactivite et Environnement (ICARE) of the Centre National de la Recherche Scientifique (CNRS) in Orleans (France) to address the flame propagation in hydrogen combustion during a severe accident. The ENACCEF2 facility is a vertical tube of 7.65 m height and 0.23 m inner diameter. In the lower part of the tube, annular obstacles are installed to promote turbulent flame propagation. At the initiative of the MITHYGENE project consortium and the European Technical Safety Organisation Network (ETSON), a benchmark on hydrogen combustion was organised with the goal to identify the current level of the computational tools in the area of hydrogen combustion simulation under conditions typical for safety considerations for NPP. In the proposed paper, the simulation results obtained by participating organizations, using both Computational Fluid Dynamics (CFD) and lumped-parameter computer codes, are compared to experimental results and analysed.

論文

EBR-II passive safety demonstration tests benchmark analyses; Phase 2

Briggs, L.*; Monti, S.*; Hu, W.*; Sui, D.*; Su, G. H.*; Maas, L.*; Vezzoni, B.*; Partha Sarathy, U.*; Del Nevo, A.*; Petruzzi, A.*; et al.

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.3030 - 3043, 2015/08

IAEA主催の「EBR-II炉停止のための熱除去試験に係るベンチマーク解析」研究共同プロジェクトは4年計画のうち3年目となっている。本プロジェクトには11ヶ国19機関がEBR-IIで行われた炉停止のための熱除去試験の内最も厳しい過渡試験の内の2ケースについて解析を実施してきた。ベンチマーク仕様に基づき炉心及び1次主冷却系の解析モデルを構築し解析を実施した。本プロジェクトのPhese 1ではブラインド解析が実施され測定データと比較・評価された。Phase 2では、Phese 1で試験データと合わなかった箇所を検討し解析モデルの改良を実施した。本論文では、最新の解析結果及び残された作業の実施方針を記載した。

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