Heat transfer coefficient modeling for downward saturated boiling flows in vertical pipes

和田 裕貴; 柴本 泰照; 日引 俊詞*

International Journal of Heat and Mass Transfer, 249, p.127219_1 - 127219_16, 2025/10

https://doi.org/10.1016/j.ijheatmasstransfer.2025.127219

Two saturated boiling heat transfer correlations for downward flows in vertical circular pipes depending on wall superheat or wall heat flux as input parameters were developed based on a heat transfer experimental database. Owing to the absence of heat transfer correlations specifically developed for downward flows, existing heat transfer correlations for different flow directions were evaluated to determine their applicability to predicting the downward flow heat transfer coefficient. The results revealed that even the most accurate correlation showed a mean absolute percentage error (MAPE) of 66.5%, highlighting the need for improving predictive performance. In response, the downward flow heat transfer correlation was modeled by integrating a nucleate boiling heat transfer term and a forced convection heat transfer term. The Dong-Hibiki correlation, a two-component, two-phase heat transfer correlation for downward flows, was adopted for the forced convection heat transfer term. The Forster-Zuber correlation, developed as a wall superheat function, and the Cooper correlation, developed as a wall heat flux function, were used for the nucleate boiling term to develop the heat transfer correlations where either wall superheat or wall heat flux is known. Notably, the Dong-Hibiki correlation has been validated over a wide range of experimental conditions. A correction factor was applied to the nucleate boiling term to address errors caused by applying Foster-Zuber and Cooper correlations to downward flows. The two developed correlations achieved an MAPE value of approximately 20%, representing an improvement of roughly 40% over existing correlations of heat transfer coefficients.

Experimental study on light gas transport during containment venting by using the large-scale test facility CIGMA

相馬 秀; 石垣 将宏*; 柴本 泰照

Annals of Nuclear Energy, 219, p.111455_1 - 111455_12, 2025/09

https://doi.org/10.1016/j.anucene.2025.111455

Containment venting is one of the accident mitigation measures during severe accidents in nuclear power plants for preventing overpressure failure of the containment vessels. Because of the capability of releasing hydrogen generated in the containment vessel, the hydrogen risk can be also reduced. In this study, we conducted experiments with the large-scale test facility CIGMA to investigate the light gas transport during the venting action, mainly focusing on the effect of sump water boiling caused by the vent. The CIGMA test vessel initially pressurized by steam, air, and helium (hydrogen simulant) that formed a helium-rich density stratification was depressurized with and without sump water, with different venting flow rates, and at different venting positions. As the sump water became a steam source due to flash boiling, the helium stratification was diluted and the venting time increased twofold compared to the case without sump water, which significantly affected the amount of helium discharged to the atmosphere. Especially for the high venting flow rate condition, the amount of helium remaining in the vessel at the end of depressurization was half that of the case without sump water. Lowering the venting position from within the initial stratification to 3 m below its interface led to a threefold increase in the amount of helium remaining at the same low pressure, because of the longer time until the helium-rich stratification reached the venting position.

Impact of molybdenum on iodine chemistry during fission product transport phenomenology

Rizaal, M.; 中島 邦久; 鈴木 恵理子; 三輪 周平

Annals of Nuclear Energy, 218, p.111433_1 - 111433_10, 2025/08

https://doi.org/10.1016/j.anucene.2025.111433

The release of iodine in a case of severe nuclear accident is directly linked to short-term radiological consequences. This concern raises issues in understanding the chemical forms of the transported iodine to devise proper accident management measures/strategies. In contributing to such efforts, this work presents experimental and theoretical approaches to defining the impact of molybdenum as a semi-volatile fission product toward iodine speciation in the gas phase. Given humid atmospheric conditions with different oxygen potentials, the interactions were revealed through the reaction products consisting of both gas and aerosols upon their transport and condensation in the temperature range of 1150-450 K. Through thermodynamic equilibrium calculations where new thermodynamic data of cesium molybdates have been incorporated, the experimental observation was reproduced, hence general interaction mechanism was proposed in this work.

Non-condensable gas accumulation and distribution due to condensation in the CIGMA Facility; Implications for Fukushima Daiichi Unit 3 (1F3)

Hamdani, A.; 相馬 秀; 安部 諭; 柴本 泰照

Progress in Nuclear Energy, 185, p.105771_1 - 105771_13, 2025/07

https://doi.org/10.1016/j.pnucene.2025.105771

This study, motivated by previous TEPSYS analysis, examined how different temperatures on the 4th and 5th floors of the Fukushima Daiichi Unit 3 reactor building (R/B) influenced non-condensable gas distribution during the 2011 severe accident. Understanding this is vital for assessing risks related to gas accumulation, especially since the hydrogen explosion may have involved multiple stages. An experimental study was conducted using the CIGMA facility, designed to mimic the R/B structure, where steam and helium (as a substitute for hydrogen) were injected for 10,000 seconds to simulate leakage. Two cooling conditions were tested: 50C (Case 1) and 90C (Case 2). Results showed that the highest concentration of non-condensable gases was often found downstream rather than near the injection point. In Case 1, after 10,000 seconds, helium concentration reached 65% in the middle region (4th floor) and 45% in the top region (5th floor). Analysis indicated that the gas mixture in the middle region posed a potential detonation risk. This study offers crucial insights for enhancing safety measures and risk mitigation strategies in nuclear reactor designs.

Steam Explosion Simulation Code JASMINE v.3 User's Guide; Revised for code version 3.3c

岩澤 譲; 松本 俊慶; 森山 清史*

JAEA-Data/Code 2025-001, 199 Pages, 2025/06

JAEA-Data-Code-2025-001.pdf:9.71MB

水蒸気爆発では、揮発性を有する低温の液体に高温の液体が接触した場合に高温の液体から低温の液体への急激な熱伝達により、高温の液体の細粒化と低温の液体の爆発的な相変化が連鎖的に発生する。爆発的な相変化により発生する衝撃波は低温の液体の内部を伝播する。衝撃波の伝播に伴い高温の液体と低温の液体の混合物が膨張することにより、周囲に存在する構造体に機械的な負荷を与える可能性がある。軽水炉のシビアアクシデントでは、原子炉格納容器へ移行した溶融炉心(溶融物)と冷却水との相互作用に起因して発生する水蒸気爆発が原子炉格納容器の健全性に対する脅威となることが想定される。このことから、水蒸気爆発の発生が周囲に存在する構造体へ与える機械的な負荷を評価することが安全評価の観点から重要となる。原子力機構では、実際の原子炉にて発生した水蒸気爆発が周囲に存在する構造体へ与える機械的な負荷を評価することを目的としてJASMINEコードを開発した。機構論的な手法を取り入れることにより、JASMINEコードは水蒸気爆発を数値解析上で取り扱うことができる。本書はJASMINEコードに採用されている基礎方程式、数値解法及び数値解析例を記載した取扱説明書である。本書に記載した数値解析例を参照することにより、JASMINEコードによる数値解析で得られた結果を検証できるように配慮した。入力条件の作成方法、コードの実行手順及び補助ツールの使用方法を記載することにより、JASMINEコードを用いた数値解析を実践できるよう配慮した。本書は「水蒸気爆発解析コードJASMINE v.3ユーザーズガイド(JAEA-Data/Code 2008-014)」の改訂版である。公開されているJASMINE 3.3bの軽微な不具合の修正に加えて、UNIX 系システムで広く使用されているGNU コンパイラー等に適合するための修正を施した最新版を JASMINE 3.3cとした。改訂版は、新規に公開される JASMINE 3.3cによる数値解析の結果に基づき作成されているために、掲載されている数値解析の結果を再現できる。数値解析の実施に際しては、既存研究により提案されている調整係数の決定方法を採用した。

Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes

佐藤 聡; 和田 裕貴; 柴本 泰照

Nuclear Engineering and Design, 437, p.114020_1 - 114020_14, 2025/06

https://doi.org/10.1016/j.nucengdes.2025.114020

沸騰遷移後(ポストBT)の熱伝達は、軽水炉における異常過渡および事故時の被覆管表面のドライアウト継続時間やピーク温度を分析する上で不可欠である。ドライアウト継続時間の評価には、リウェット現象が非常に重要だが、高流量および高熱流束条件下でのリウェット速度に関する実験データベースが不足しているため、モデルの開発および検証に十分なデータが存在しない。そこで、単管実験装置を用いて、幅広い熱水力条件下でステップ状の境界条件の変化によって生じるリウェット速度に関するデータベースを構築した。このデータベースと得られたリウェット速度の特性に基づいて、リウェット速度の実験的相関式を提案した。この相関式は、ステップ状過渡変化における液相または気相の質量フラックスの変化をパラメータとして用いることで、リウェット速度を正確に予測する。これは、再冠水過程と比較して、極めて高い質量流束条件下では、液膜前面近傍における気相または液相の質量流束の変化がリウェットに強く影響することを示唆している。

Nickel binding with magnetite nanoparticles

Fablet, L.*; Pdrot, M.*; Choueikani, F.*; Kieffer, I.*; Proux, O.*; Pierson-Wickmann, A.-C.*; Cagniart, V.*; 蓬田 匠; Marsac, R.*

Environmental Science; Nano, 12(5), p.2815 - 2827, 2025/05

https://doi.org/10.1039/d4en01114g

ニッケル(Ni)は環境中に遍在する微量元素である。Niは酸化鉄ナノ粒子との親和性が高く、土壌や水中から酸化鉄ナノ粒子、特に環境中に普遍的に存在する磁鉄鉱によって除去することができれば、環境浄化のための新たな戦略の1つとなり、その研究の意義は大きい。しかし、磁鉄鉱の化学量論(Fe(II)とFe(III)の比率)を制御することが困難であるため、Niと磁鉄鉱の相互作用は十分に理解されていなかった。そこで本研究では、異なるFe(II)とFe(III)の比率を持つ磁鉄鉱ナノ粒子を用い、吸着実験とX線吸収分光法によって溶液中と嫌気雰囲気下におけるNiと磁鉄鉱の相互作用を調べた。この研究により明らかにされた磁鉄鉱とNiの相互作用は、将来的にNi汚染の環境浄化戦略を立案する上で重要な知見となりうる。

Evaluating the effect of temporal variations in wind speed on sheltering effectiveness and developing a simplified correction method to account for these variations

廣内 淳; 高原 省五; 渡邊 正敏*

Journal of Radiological Protection, 45(2), p.021506_1 - 021506_13, 2025/05

https://doi.org/10.1088/1361-6498/add53e

屋内退避は原子力発電所事故時の放射線被ばくを緩和するための重要な防護措置である。吸入被ばくを低減する屋内退避の効果は一般的に屋内外の積算線量の比である低減係数を用いて評価される。屋内での線量は主に自然換気率、浸透率、室内での沈着率に依存する。加えて、自然換気率は風速に依存する。今までの研究では、低減係数は一定値として扱われるか、風速一定の条件で計算された。しかしながら、実際には風速は変動する。本研究では風速の時間変化による低減係数への影響を調査し、これら変動を考慮するための簡易的な補正方法を開発した。結果として、風速の時間変化はファクター2程度の低減係数の違いを生じさせることを示した。さらに簡易補正方法を用いることで、補正した低減係数は、実際の風速変動を利用して計算した低減係数と平均で10%以内で一致した。さらに計算コストは20倍以上削減できることを示した。

Heat transfer characteristics of downward saturated boiling flow in vertical round pipes

和田 裕貴; 柴本 泰照; 日引 俊*

International Journal of Heat and Mass Transfer, 239, p.126598_1 - 126598_18, 2025/04

https://doi.org/10.1016/j.ijheatmasstransfer.2024.126598

This study reviewed the saturated boiling heat transfer research in downward flows. A database of downward flow heat transfer experiments was created using experimental studies. Saturated boiling heat transfer correlations in internal flows were collected, and no downward flow-specific heat transfer correlations were identified. The applicability of heat transfer correlations to downward flow heat transfer experiments was evaluated, and no correlation could predict the heat transfer coefficients accurately for all experimental databases. However, correlations that could predict heat transfer coefficients reasonably well were determined for each channel size. Cooper's correlation [Int. Chem. Eng. Symp. Ser. 86 (1984) 785-792] had a mean absolute percentage error (MAPE) of 11.7% for mini-channels and Kim and Mudawar's correlation [Int. J. Heat Mass Transf. 64 (2013) 1239-1256] had an MAPE of 66.5% for macro-channels. Furthermore, because the advection direction between the liquid-phase and the generated bubbles differed depending on the liquid-phase velocity in downward flows, we evaluated the prediction performance of the heat transfer coefficient for the liquid-phase velocity. For some experimental data, the prediction performance of the existing correlation for downward flow heat transfer worsened as the advection velocity of the bubbles decreased. This result is one of the issues to be addressed in the future development of heat transfer correlations.

Development of scaling parameter S for negative stress ratios R based on trend in experimental data for fatigue crack growth rates of austenitic stainless steels for ASME code Section XI

Negyesi, M.*; 山口 義仁; 長谷川 邦夫; Lacroix, V.*; Morley, A.*

Journal of Pressure Vessel Technology, 147(2), p.021201_1 - 021201_7, 2025/04

https://doi.org/10.1115/1.4067484

Fatigue crack growth rates for stainless steels in air environment are provided by the ASME Code Section XI. When the stress ratio R is positive from 0 to 1, the scaling parameter SR increases with the increasing ratio R, and the crack growth rates increase with the increasing stress ratio R. When R is less than 0, the parameter SR=1. Hence, fatigue crack growth rates under negative R ratios are independent of stress ratios R according to the ASME Code Section XI. However, from the literature survey, experimental data reveal that the fatigue crack growth rates decreases with decreasing R ratios below zero. The objective of this paper is to assess fatigue crack growth rates under such negative stress ratios for stainless steels in air environment. An equation determined from trends in experimental data surveyed in this study is proposed for negative stress R ratios to calculate the parameter SR for the ASME Code Section XI.