検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年
検索結果: 4 件中 1件目~4件目を表示
  • 1

発表形式

Initialising ...

選択項目を絞り込む

掲載資料名

Initialising ...

発表会議名

Initialising ...

筆頭著者名

Initialising ...

キーワード

Initialising ...

使用言語

Initialising ...

発行年

Initialising ...

開催年

Initialising ...

選択した検索結果をダウンロード

論文

High temperature reaction of multiple eutectic-component system; The Case of solid metallic Zr and molten stainless steel-B$$_{4}$$C

墨田 岳大; 小畠 雅明; 高野 公秀; 池田 篤史

Materialia, 20, p.101197_1 - 101197_11, 2021/12

The eutectic melting, one of the fundamental phenomena in high temperature reactions involving liquid phases, is a primitive but important subject for both scientific and industrial fields associated with metallurgy. The present study aims at revealing the formation and reaction mechanisms of the multiple eutectic-component system consisting of solid metallic Zr and molten stainless steel- boron carbide (SS-B$$_{4}$$C) by combining multiple analytical methods (i.e. powder X-ray diffraction (PXRD), scanning electron microscopy- energy dispersive X-ray spectroscopy (SEM-EDS), and dynamic secondary ion mass spectrometry (D-SIMS)) with thermodynamical consideration. The results indicate that the solidified Zr-SS-B$$_{4}$$C mixture is composed of major phases of (Fe,Cr)$$_{2}$$Zr, (Fe,Cr,Ni)$$_{2}$$Zr, (Ni,Fe)Zr$$_{2}$$, ZrB$$_{2}$$, and a minor phase of ZrC. The results also reveal that the eutectic melting between solid metallic Zr and molten SS-B$$_{4}$$C can be described as the combination of diffusion kinetics and thermodynamic stability. That is, the initial formation of ZrC and ZrB$$_{2}$$ layers at the reaction interface significantly retards the diffusion of other SS-B$$_{4}$$C components (i.e. Cr, Fe, and Ni) into solid metallic Zr.

論文

Solidification and re-melting mechanisms of SUS-B$$_{4}$$C eutectic mixture

墨田 岳大; 北垣 徹; 高野 公秀; 池田 篤史

Journal of Nuclear Materials, 543, p.152527_1 - 152527_15, 2021/01

 被引用回数:2 パーセンタイル:81.22(Materials Science, Multidisciplinary)

Fundamental understanding of the high-temperature interaction between stainless steel (SUS) and B$$_{4}$$C is indispensable for estimating and characterizing the fuel debris generated during severe accidents of boiling water reactors (BWR), such as Fukushima Dai-ichi Nuclear Power Station (FDNPS, also referred to as "1F") in Japan. This study aims at systematically characterizing the solidified products of molten SUS-B$$_{4}$$C mixtures by powder X-ray diffraction (PXRD), scanning electron microscopy- energy dispersive X-ray spectroscopy (SEM-EDS), and thermogravimetry-differential thermal analysis (TG-DTA) with a range of the B$$_{4}$$C content relevant to the fuel debris composition expected at 1F, in order to elucidate the solidification and re-melting mechanisms. The results indicated that $$gamma$$-Fe and (Cr,Fe)$$_{2}$$B are the major solidified phases when the B$$_{4}$$C content is below 3 mass%, while (Cr,Fe)$$_{23}$$(C,B)$$_{6}$$ is formed as an additional third phase when the B$$_{4}$$C content exceeds 3 mass%. The solidification of molten SUS-B$$_{4}$$C mixture and re-melting of solidified SUS-B$$_{4}$$C melt are eutectic, which is mainly controlled by the pseudo-binary Fe-B system that is influenced by the C and Cr content and additional minor components such as Mo.

口頭

高温・高圧水蒸気環境下における原子炉構造材へのCs吸着挙動評価

墨田 岳大*; 米川 夏津夫*; 関尾 佳弘; 佐藤 勇*; 小林 能直*; 逢坂 正彦; 前田 宏治; 赤坂 尚昭

no journal, , 

福島第一原子力発電所(1F)事故において1-3号機では燃料溶融により核分裂生成物(FP)である$$^{137}$$Cs, $$^{133}$$Iなどの高放射性核種が主として放出され、圧力容器内の構造材料部分ばかりでなく原子炉建屋内が高線量化した。今後1Fの廃止措置を進めるにあたり、適切な燃料デブリ取出し手法やアクセスルート(人の動線及び遠隔装置の経路など)の確立、炉内の低線量化及び除染の手法の決定を行うためには、シビアアクシデント(SA)時におけるCs化合物の炉内構造材料等への吸着挙動に関する知見を取得する必要がある。しかしながら、既往研究は大気圧下のみで行われており、SA環境を模擬した高圧下でのCs化合物の炉内構造材料への吸着挙動評価の例はない。本試験では、温度・圧力・雰囲気の制御が可能なCs吸着挙動評価装置を開発し、基礎試験としてSA模擬条件下でSUS304L材に対するCsIの吸着挙動に係る試験・評価を行った。吸着試験後の試料観察と元素分析から、試験片へのCsIの吸着量は、雰囲気や水蒸気の有無よりも、圧力の寄与が大きい傾向にあることが示唆された。

口頭

福島第一原発(1F)における金属系燃料デブリ成分の凝固・再溶融機構の検討

墨田 岳大

no journal, , 

Fundamental understanding of the high-temperature interaction between stainless steel and B$$_{4}$$C is indispensable for estimating and characterizing the fuel debris generated during severe accidents of Fukushima Dai-ichi Nuclear Power Station (FDNPS, also referred to as "1F") in Japan. This study aims at systematically characterizing the solidified products of molten SUS-B$$_{4}$$C mixtures by powder X-ray diffraction (PXRD), scanning electron microscopy- energy dispersive X-ray spectroscopy (SEM-EDS), and thermogravimetry-differential thermal analysis (TG-DTA) with a range of the B$$_{4}$$C content relevant to the fuel debris composition expected at FDNPPs, in order to elucidate the solidification and re-melting mechanisms.

4 件中 1件目~4件目を表示
  • 1