Experimental analysis of non-condensable gas and steam distribution due to condensation in the CIGMA facility simulating the reactor building

Hamdani, A.; 相馬 秀; 安部 諭; 柴本 泰照

Nuclear Engineering and Technology, 9 Pages, 2026/00

https://doi.org/10.1016/j.net.2026.104219

This study experimentally investigates non-condensable gas transport induced by steam condensation using the CIGMA facility, simulating reactor building conditions of Fukushima Daiichi Unit 3 during a severe accident. Steam and helium, used as a hydrogen surrogate, were continuously injected into the CIGMA's vessel equipped with partition plates representing the hierarchical structure of the reactor building. Parametric experiments were conducted by varying flow path ratio, steam-to-helium mass ratio, and cooling conditions. The results show that steam condensation is the dominant mechanism controlling non-condensable gas accumulation by increasing the relative concentration of helium. The highest helium concentrations generally occur below the injection point rather than at the injection elevation, indicating downward transport followed by condensation-driven accumulation. Shapiro ternary diagram analysis indicates that condensation-driven changes in gas composition lead to prolonged residence within flammability and detonation regions. These findings highlight the critical role of condensation in hydrogen distribution and provide experimental insight relevant to hydrogen risk assessment and mitigation in reactor buildings during severe accidents.

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.

Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow

上澤 伸一郎; 小野 綾子; 永武 拓; 山下 晋; 吉田 啓之

Journal of Nuclear Science and Technology, 62(5), p.432 - 456, 2025/05

https://doi.org/10.1080/00223131.2024.2447366

ワイヤメッシュセンサ(WMS)の精度を明らかにするため、単一の球形気泡と気泡流に対してWMSの静電場シミュレーションを実施した。単一気泡の静電場シミュレーションでは、様々な気泡位置における電流密度分布と、送信ワイヤから受信ワイヤまでの電流経路を示した。その結果、WMS周囲の不均一な電流密度分布に基づく系統的誤差があることを明らかにした。また、数値流体解析コードJAEA Utility Program for Interdisciplinary Thermal-hydraulics Engineering and Research (JUPITER)で得られた気泡流結果に対して静電場シミュレーションを実施したところ、線形近似やMaxwellの式などの、WMS信号からボイド率への既存の変換方法では0と1の間の瞬間ボイド率の中間値を定量的に推定できなかった。また、WMS信号に対してボイド率0.2という大きなばらつきがあり、瞬間ボイド率を定量的に計測することが困難であることがわかった。一方で、時間平均ボイド率においては、流路の中心付近のボイド率は線形近似を使用して推定でき、流路壁面近くのボイド率はMaxwellの式を使用して推定できることがわかった。

Transient behavior of a boiling water reactor-type offshore floating nuclear power plant during platform motion

福田 航大; 小原 徹*

Nuclear Technology, 12 Pages, 2025/00

https://doi.org/10.1080/00295450.2025.2502266

Offshore floating nuclear power plants (OFNPs) are gaining attention as safe and location-flexible means for nuclear energy utilization. Although platform motion in the marine environment may affect reactor kinetics, particularly in boiling water reactors (BWRs), BWR-type OFNPs are expected to have high economic efficiency. This study investigated the reactor power behavior of a BWR-type OFNP using three-dimensional transient neutronics-thermal hydraulics coupled analysis. Heave and pitch motions were considered under realistic wave conditions using a typical BWR model. The results show that the reactor power and its distribution can vary because of the wave-induced platform motion; however, the amplitude of these variations is sufficiently small to ensure normal operation, even under the extreme wave conditions of a one-in-10,000-year storm. Although the results of the present study demonstrate the ability of BWR-type OFNPs to provide a safe and stable energy supply, they also suggest the need for further research. Further studies are needed to address the complex wave conditions and assess the effects of the platform motion on ancillary systems, such as recirculation systems.

再処理施設の高レベル廃液蒸発乾固事故での廃液沸騰時の貯槽内化学挙動試解析

吉田 一雄; 桧山 美奈*; 玉置 等史

JAEA-Research 2024-007, 24 Pages, 2024/08

JAEA-Research-2024-007.pdf:2.1MB

再処理施設の過酷事故の一つである高レベル放射性廃液貯槽の冷却機能喪失による蒸発乾固事故では、沸騰により廃液貯槽から発生する硝酸-水混合蒸気とともにルテニウム(Ru)の揮発性の化学種(RuO)が放出される。このためリスク評価の観点からは、Ruの定量的な放出量の評価が重要な課題である。RuOの発生現象には、廃液の溶媒である硝酸の放射線分解で発生する亜硝酸が沸騰段階でのRuOの発生を抑制することが実験的に示されている。この現象を解析的に取り扱うには、廃液の当該事故時の硝酸及び亜硝酸を含めた窒素化合物の化学変化の解析が必要となる。廃液貯槽沸騰模擬コード:SHAWEDでは、硝酸-水-FP硝酸塩系での気液平衡の仮定に基づき廃液の温度上昇、硝酸及び水の蒸発量、気泡破裂に伴う飛沫生成量を計算する。現状の解析では、廃液中の亜硝酸濃度等の変化を模擬できない。より現象に即した模擬を可能にするため当該事故時の施設内の化学的な挙動を解析するSCHERNをSHAWEDと結合させ、放射線分解による亜硝酸の生成も考慮した廃液貯槽内の熱流動挙動解析及び化学挙動解析を同時に可能とするよう改良した。本報では、両計算コードを結合した計算の流れ、両者間でのデータの授受を概説し模擬結果の一例を示す。

Impact of interatomic structural characteristics of aluminosilicate hydrate on the mechanical properties of metakaolin-based geopolymer

Kim, G.*; Cho, S.-M.*; Im, S.*; Suh, H.*; 諸岡 聡; 菖蒲 敬久; 兼松 学*; 町田 晃彦*; Bae, S.*

Construction and Building Materials, 411, p.134529_1 - 134529_18, 2024/01

https://doi.org/10.1016/j.conbuildmat.2023.134529

This study explores the influence of the interatomic structure of sodium aluminosilicate hydrate (N-A-S-H) with varying silica contents on the mechanical properties of metakaolin-based geopolymer. Geopolymer pastes comprising Si/Al ratios between 2.0 and 3.0 were synthesized. A larger number of Si-O-Si linkages compared to Si-O-Al linkages and a higher atomic number density were found in the geopolymers with higher silica contents, which enhanced the compressive strength of the geopolymer pastes up to the optimal Si/Al ratio of 2.5. The paste with a Si/Al = 2.5 exhibited a greater portion of Q(1Al and 2Al) and denser morphology compared to the other geopolymer pastes. Furthermore, in-situ high-energy synchrotron X-ray scattering experiments were conducted to assess the elastic modulus of the aluminosilicate structure at a local atomic scale. The modulus value in real space decreases with increasing silica contents up to Si/Al = 2.5 and increases with the presence of excessive unreacted silica fume. The modulus value in reciprocal space for the axial and lateral directions both presented a positive value at the geopolymer comprising a Si/Al ratio higher than 2.5, indicating that the load-bearing property of N-A-S-H changed at higher Si/Al ratios. Moreover, the smallest difference between the strains along the axial and lateral directions was detected for the geopolymer with Si/Al = 2.5 in both the real and reciprocal space, owing to the most interconnected and flexible nanostructure, which led to the highest mechanical strength.

再処理施設の高レベル廃液蒸発乾固事故のソースターム解析手法の整備

吉田 一雄; 玉置 等史; 桧山 美奈*

JAEA-Research 2023-001, 26 Pages, 2023/05

JAEA-Research-2023-001.pdf:1.61MB

再処理施設の過酷事故の一つである高レベル放射性廃液貯槽の冷却機能喪失による蒸発乾固事故では、沸騰により廃液貯槽から発生する硝酸-水混合蒸気とともにルテニウム(Ru)の揮発性の化学種が放出される。このためリスク評価の観点からは、Ruの定量的な放出量の評価が重要な課題である。再処理施設のリスク評価の精度向上に資するため、計算プログラムを用いて当該事故時でのソースタームを解析的に評価する手法の整備を進めている。提案する解析手法では、まず廃液貯槽の沸騰をSHAWEDで模擬する。模擬結果の蒸気発生量等を境界条件としてMELCORにより施設内の蒸気等の流れに沿って各区画内の熱流動状態を模擬する。さらに各区画内の熱流動状態を境界条件としてSCHERNを用いてRuを含む硝酸、NO等の化学挙動を模擬し、施設外への放射性物質の移行量(ソースターム)を求める。本報では、仮想の実規模施設での当該事故を想定して、これら3つの計算プログラム間でのデータの授受を含めて解析事例を示す。

Conformation, hydration, and ligand exchange process of ruthenium nitrosyl complexes in aqueous solution; Free-energy calculations by a combination of molecular-orbital theories and different solvent models

城戸 健太朗; 金子 政志

Journal of Computational Chemistry, 44(4), p.546 - 558, 2023/02

AA2022-0469.pdf:1.33MB

https://doi.org/10.1002/jcc.27021

Distribution of solvent molecules near transition-metal complex is key information to comprehend the functionality, reactivity and so on. However, polarizable continuum solvent models still are the standard and conventional partner of molecular-orbital (MO) calculations in the solution system including transition-metal complex. In this study, we investigate the conformation, hydration structure and ligand substitution reaction between NO and HO in aqueous solution for [Ru(NO)(OH)(NO)] (), [Ru(NO)(OH)(NO)(ONO)] () and [Ru(NO)(OH)(NO)(HO)] () using a combination method of MO theories and a state-of-the-art molecular solvation technique (NI-MC-MOZ-SCF). In the complexes, the treatment is essentially required because except for nitrosyl ligand, a strong hydrogen bond is formed between the ligand and solvent water. These results are complementary to the data previously obtained by N NMR experiment. A dominant species is found in the complex conformers and, as expected, different between the solvent models, which reveals that molecular solvation beyond continuum media treatment are required for a reliable description of solvation near transition-metal complex. In the stability constant evaluation of ligand substitution reaction, similar to the previous reports, an assumption that considers the direct association between the dissociated nitrite anion and complex is useful to obtain a reliable stability constant.

CFD analysis on stratification dissolution and breakup of the air-helium gas mixture by natural convection in a large-scale enclosed vessel

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

https://doi.org/10.1016/j.pnucene.2022.104415

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.

Effect of magnesium silicate hydrate (M-S-H) formation on the local atomic arrangements and mechanical properties of calcium silicate hydrate (C-S-H); In situ X-ray scattering study

Kim, G.*; Im, S.*; Jee, H.*; Suh, H.*; Cho, S.*; 兼松 学*; 諸岡 聡; 小山 拓*; 西尾 悠平*; 町田 晃彦*; et al.

Cement and Concrete Research, 159, p.106869_1 - 106869_17, 2022/09

https://doi.org/10.1016/j.cemconres.2022.106869

This study explored the effect of M-S-H formation on the local atomic arrangements and mechanical properties of C-S-H. The elastic moduli of the samples were calculated using shifted atomic distances (r) and d-spacings (d) acquired by applying an external load on the pastes during X-ray scattering experiments. The experimental results indicated that the crystal structure of C-S-H remained intact with MgCl addition. At the highest Mg/Si ratio (Ca/Si = 0.6, Mg/Si = 0.2), change in the dominant phase occurred from C-S-H to M-S-H because the low pH environment hindered the formation of C-S-H and facilitated the formation of M-S-H. The elastic modulus decreased with increasing Mg/Si ratio up to 0.1 owing to both C-S-H destabilization and low M-S-H content in the samples. Conversely, the elastic modulus increased in the paste synthesized with the highest Mg/Si ratio because considerable M-S-H had formed, which exhibited a higher elastic modulus than C-S-H.