Study on dryout and rewetting during accidents including ATWS for the BWR at JAEA

佐藤 聡; 和田 裕貴; 柴本 泰照; 与能本 泰介

Nuclear Engineering and Design, 354, p.110164_1 - 110164_10, 2019/12

https://doi.org/10.1016/j.nucengdes.2019.110164

原子力機構ではBWRの沸騰後遷移熱伝達、過渡限界熱流束及びリウェットに関する一連の実験研究を行ってきた。これまでに、異常過渡条件をカバーする実験データベースが開発されており、またリウェット現象における先行冷却の重要性が認識されるようになった。本論文では、原子炉停止機能喪失事象、炉心熱伝達へのスペーサの効果、機構論的モデル開発のための現象の物理的理解に焦点を当て、これまでに得られた主な結果と共に、本研究のアプローチを提示した。

Experimental investigation of decontamination factor dependence on aerosol concentration in pool scrubbing

孫 昊旻; 柴本 泰照; 岡垣 百合亜; 与能本 泰介

Science and Technology of Nuclear Installations, 2019, p.1743982_1 - 1743982_15, 2019/06

https://doi.org/10.1155/2019/1743982

Because a pool scrubbing is important for reducing radioactive aerosols to the environment for a nuclear reactor in a severe accident situation, many researches have been performed. However, decontamination factor (DF) dependence on aerosol concentration was seldom considered. DF dependence in the pool scrubbing with 2.4 m water submergence was investigated by light scattering aerosol spectrometers. It was observed that DF increased monotonically as decreasing particle number concentration in a constant thermohydraulic condition. Two validation experiments were conducted to confirm the observed DF dependence. In addition, characteristics of the DF dependence in different water submergences were investigated experimentally. It was found the DF dependence became more significant in higher water submergence.

Influence of grating type obstacle on stratification breakup by a vertical jet

安部 諭; 石垣 将宏; 柴本 泰照; 与能本 泰介

Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) (USB Flash Drive), 9 Pages, 2018/10

At Japan Atomic Energy Agency (JAEA), small scale experiment, named VIMES (VIsualization and MEasurement system on stratification behavior) experiment, has been performed since 2014. In this paper, we introduce the influence of grating type obstacle to the VIMES experiment. Two types of grating obstacle were constructed based on the aperture area ratio. The obstacles were placed at the intermediate position between the jet nozzle exit and bottom of the initial stratification. Experimental results showed that the vertical jet was strongly affected by the grating obstacle. Due to the rectifying effect, the radial spreading was suppressed and the velocity magnitude on the jet center line became larger than that in case without the grating obstacle. Meanwhile, due to the resistance effect, the integral momentum flux of the vertical jet was decayed with decrease of the aperture area ratio. It means that in case with the grating obstacle the integral jet penetration strength was decayed, although the local jet penetration to the stratification was stronger than that in case without the grating obstacle. Also, the slower stratification breakup could be observed with decrease of the aperture area ratio, indicating that stratification breakup rate to be discussed in detail considering every possible effect of a jet penetration.

On the liquid film flow characteristics during the rewetting in the single rod air-water system

和田 裕貴; Le, T. D.; 佐藤 聡; 柴本 泰照; 与能本 泰介

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 10 Pages, 2018/07

Dry-out and rewet for an anticipated transition without scrum (ATWS) become one of the important issues. In order to predict all of these phenomena, it is necessary to cover wide range of thermal-hydraulic condition, and the modeling of precursory cooling is one of the key issues on the prediction. To reveal the precursory cooling phenomena in the rewetting process, rewetting experiment was carried out using a single heater rod in a circular glass pipe with air-water system at atmospheric pressure. Liquid film front thermal and dynamic behaviors were measured by thermocouples and visualization with a high speed camera. To establish a new rewetting model, liquid film flow characteristics including roll wave behavior, and the mass and energy balance of the liquid film at the rewetting front considering effects of sputtering were summarized in this paper.

Experimental investigation of Post-BT heat transfer and rewetting phenomena

佐藤 聡; 和田 裕貴; Le, T. D.; 柴本 泰照; 与能本 泰介

Proceedings of ANS International Conference on Best Estimate Plus Uncertainties Methods (BEPU 2018) (USB Flash Drive), 12 Pages, 2018/00

本研究では、Post-BT熱伝達、液滴伝達率およびリウェット挙動を取得するため、BWRのAOOを模擬した条件において実験を行った。熱伝導方程式を解析的に解くことでリウェット挙動を調査し、リウェット速度、壁面温度および先行冷却と濡れ領域における熱伝達率の間の関係を把握した。さらに、Post-BT熱伝達とリウェット挙動へのスペーサ効果を調べるため、ATWS模擬条件において丸セル模擬スペーサを設置した実験を行った。これにより熱伝達率がモデルによる予測よりも増加すること、また低圧、高質量流束条件においてリウェット速度が増加することが示された。一連の実験を通して先行冷却が重要な役割を果たしていると考えられることから、先行冷却に着目した新しい実験を行い、リウェットフロント周辺の液膜と液滴の挙動が先行冷却メカニズムに与える影響を調べた。

Experimental study on outer surface cooling of containment vessel by using CIGMA

柴本 泰照; 石垣 将宏; 安部 諭; 与能本 泰介

Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 14 Pages, 2017/09

The present paper introduces the recent outcome from the CIGMA experiments regarding containment vessel cooling, in which an external side of a vessel upper head was flooded by water. The test vessel was initially pressurized by steam and noncondensable gas (air and/or helium), and was subsequently cooled by pouring water to the outside of the vessel top. Similar experiments were performed by authors using air-steam binary system in the previous study, which showed several characteristic phenomena such as inverse temperature stratification. The experimental conditions were extended systematically in this study to investigate the effects of initial gas composition and distribution in a vessel. The measurement results indicated that natural circulation was significantly affected by distributions of each gas species. In particular, it was enhanced when the gas density became heavier after condensation on the vessel inner wall, while it was suppressed when the gas density became lighter, creating density stratification with helium-rich gas in the upper region. The results are explained by the simplified model.

CFD simulation of a CIGMA experiment CC-PL-04 on the containment thermal hydraulics affected by the outer surface cooling

石垣 将宏; 安部 諭; 柴本 泰照; 与能本 泰介

Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 10 Pages, 2016/11

原子力機構ではシビアアクシデント時の格納容器内熱水力挙動把握のため、大型格納容器実験装置CIGMAを製作し、実験を行っている。本発表では、蒸気及び空気の混合気体を封入した容器における外面冷却実験CC-PL-04についてCFDコードOpenFOAMにより解析した結果を報告する。

Heat conduction analyses on rewetting front propagation during transients beyond anticipated operational occurrences for BWRs

与能本 泰介; 柴本 泰照; 佐藤 聡; 岡垣 百合亜

Journal of Nuclear Science and Technology, 53(9), p.1342 - 1352, 2016/09

AA2015-0497.pdf:1.05MB

https://doi.org/10.1080/00223131.2015.1108882

BWRの運転時の異常な過渡変化を超える過渡事象におけるドライアウトした燃料表面のリウェット挙動に関して、当研究グループで以前実施した研究では、リウェット直前の冷却として定義する先行冷却により、その伝播速度が強く支配されることが示された。本研究では、この先行冷却の特徴を把握するために、実験結果に対して、さらに工学解析と熱伝導解析を実施した。特徴把握のため、まず、先行冷却を熱伝達率評価値を用いて定量的に定義し、先行冷却が開始するタイミングでの被覆管温度の関数としてリウェット速度を検討した。その結果、リウェット点近傍での最大伝熱量によりリウェット速度が制限される傾向が示され、熱伝導解析の結果と整合した。

Experimental and numerical study on density stratification erosion phenomena with a vertical buoyant jet in a small vessel

安部 諭; 石垣 将宏; 柴本 泰照; 与能本 泰介

Nuclear Engineering and Design, 303, p.203 - 213, 2016/07

https://doi.org/10.1016/j.nucengdes.2016.03.022

The Japan Atomic Energy Agency has started the ROSA-SA project to investigate thermal hydraulic phenomena in a reactor containment vessel during a severe accident. The hydrogen distribution in the vessel is one of significant safety issues in discussing a potential of hydrogen combustion in the containment. This paper focuses on a density stratification erosion and break-up mechanism with a vertical buoyant jet promoting the turbulent helium transport. Small scale experiment and computational fluid dynamics (CFD) analyses were carried out for investigating this phenomena. In the experiment, a rectangular vessel made with acrylic plates with a width of 1.5m, a length of 1.5 m and a height of 1.8 m was used for visualizing flow field with particle image velocimetry system. The quadrupole mass spectrometer system with a multiport rotating valve was applied for measuring gaseous concentration at 20 elevation points. In CFD analysis with OpenFOAM, two typical well-used turbulence models were used: low-Reynolds number type k- model and SST k- model, with a turbulence model modification to consider the buoyant effect in the stratification. As a result, the stratification erosion in the CFD analyses with the modified turbulence model agreed well with the experimental data, indicating importance of the turbulence damping by the buoyant effect.

First experiments at the CIGMA facility for investigations of LWR containment thermal hydraulics

柴本 泰照; 安部 諭; 石垣 将宏; 与能本 泰介

Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 9 Pages, 2016/06

http://doi.org/10.1115/ICONE24-60515

There has been an extensive reorientation of the light water reactor research in Japan since the Fukushima Dai-ichi Nuclear Power Station accident, which focuses on severe accidents and accident managements. The Japan Atomic Energy Agency (JAEA) initiated the ROSA-SA project in 2013 for the purpose of studying thermal hydraulics relevant to over-temperature containment damage, hydrogen risk, and fission product transport. For this purpose, the JAEA newly constructed the Containment InteGral Measurement Apparatus (CIGMA) in 2015 for the experiments addressing containment responses, separate effects, and accident managements. Recently, we successfully conducted first experiments using CIGMA to characterize the facility under typical experimental conditions investigating basic phenomena such as buildup of pressure by steam injection, containment cooling and depressurization by internal or external cooling, and density stratified layer mixing by impinging jet. This paper provides an overview of the research programs, the brief description of the facility specification and the outcomes obtained from the first experiments.