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C-stainless steel composite under severe reactor conditionsAhmed, Z.*; Kumar, R.*; 横山 諒*; 岡本 孝司*; Pellegrini, M.*; 山野 秀将
Proceedings of 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21) (Internet), 15 Pages, 2025/08
Scanning electron microscopy with energy-dispersive X-ray spectroscopy (SEM-EDS) and X-ray photoelectron spectroscopy (XPS) confirmed the formation of metal carbides and the presence of boron in the eutectic melt. Characterizations results tell that not only boron, but carbon too diffuses in the eutectic melt which is a concern of recriticality. The current findings confirm the relocation of the BC-SS eutectic mixture with diffusion and precipitation of both boron and carbon, conditions likely to occur under extreme reactor conditions.
茂木 孝介; 松本 俊慶; 塩津 弘之
Proceedings of 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21) (Internet), 10 Pages, 2025/08
Since the hydrogen explosion at the Fukushima Daiichi Nuclear Power Plants accident in March 2011, hydrogen management during severe accidents at nuclear power plants has attracted attention as an important issue. In order to improve hydrogen management under severe accident conditions, the propagation of flames and the resulting loads on structures need to be predicted accurately. For this reason, the use of computational fluid dynamics methods is expected. Various benchmark experiments have been carried out and turbulence models, turbulent combustion models and chemical reaction models have been discussed, but the uncertainties of each model have not been treated independently. Analysis including uncertainty assessment is necessary to promote efficient research activities through uncertainty-based prioritisation and to reflect the latest findings in best practice guidelines. The aim of this study is to establish a methodology for quantifying the chemical reaction uncertainty in turbulent premixed flame CFD and to perform CFD and uncertainty analyses on existing benchmark experiments.
浜瀬 枝里菜; 堂田 哲広; 小野 綾子; 田中 正暁; 三宅 康洋*; 今井 康友*
Proceedings of 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21) (Internet), 14 Pages, 2025/08
ナトリウム冷却高速炉において、浸漬型直接炉内冷却器を用いた自然循環崩壊熱除去時に生じる炉心-プレナム相互作用等の現象を低計算コストで評価するため、合理化集合体モデルを炉心部に組み込んだ炉容器内多次元熱流動解析モデル(RV-CFD)を整備している。本研究では、燃料ピンの熱容量及び熱抵抗を考慮可能な非熱平衡モデルを整備するとともに、スクラム模擬試験解析を実施して、RV-CFDの過渡解析への適用性を確認した。
堂田 哲広; 加藤 慎也; 上羽 智之; 田中 正暁; 中峯 由彰*; 井川 健一*; 飯田 将来*
Proceedings of 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21) (Internet), 14 Pages, 2025/08
ナトリウム冷却高速炉の出力増加時の炉心変形による反応度フィードバックを正確に評価するには、核、熱、炉心構造の相互作用をモデル化する必要がある。原子力機構ではこれらの現象を詳細にモデル化する解析コードを連成させる評価手法を開発した。本研究では、本評価手法をFFTF LOFWOS#13試験の炉心解析に適用し、全反応度の解析結果と試験結果を比較した。炉心構造に係る設計パラメータの感度解析結果から、炉心の湾曲挙動が全反応度の時間変化に大きな影響を与えることが確認された。
山野 秀将
no journal, ,
The contents are International Cooperation on the Development of Sodium-cooled Fast Reactors in Japan, Japanese position on international collaboration to boost of SFR/Cycle technology development in Japan, International collaboration on Sodium-cooled Fast Reactor, Successful Japan-France Collaboration on SFR, and Importance of international cooperation.
山野 秀将
no journal, ,
The contents are Demonstration Sodium-cooled Fast Reactor (SFR), Analysis code V&V and testing for design and safety analysis toward licensing, Facilities for SFR Development, Facilities for SFR Development.