Muon spin relaxation in mixed perovskite (LaAlO)(SrAlTaO) with

伊藤 孝; 髭本 亘; 幸田 章宏*; 中村 惇平*; 下村 浩一郎*

Interactions (Internet), 245(1), p.25_1 - 25_7, 2024/12

https://doi.org/10.1007/s10751-024-01866-5

We report on muon spin relaxation (SR) measurements in a mixed perovskite compound, (LaAlO)(SrAlTaO) with (LSAT), which is widely used as a single-crystalline substrate for thin film deposition. In zero applied field (ZF), muon depolarization due to the distribution of nuclear dipole fields was observed in the temperature range from 4 K to 270 K. Interestingly, SR time spectra in ZF maintained a Gaussian-like feature over the entire range, while the depolarization rate exhibited a monotonic decrease with increasing temperature. This behavior may be attributed to the thermally activated diffusion of muons between a few adjacent sites within a confined space of the angstrom scale, where the motionally averaged local field that each muon experiences can remain non-zero and result in maintaining the Gaussian-like line shape. The spatial distribution of electrostatic potential at lattice interstices evaluated via density functional theory calculations suggests that such a restriction of muon diffusion paths can be caused by the random distribution of cations with different nominal valences in the mixed perovskite lattice.

Effectiveness evaluation methodology of the measures for improving resilience of nuclear structures against excessive earthquake

栗坂 健一; 西野 裕之; 山野 秀将

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 8 Pages, 2023/05

本研究の目的は破損拡大抑制技術によって過大地震時の原子炉構造レジリエンス向上策の有効性評価手法を開発することである。安全上重要な機器・構造物のレジリエンス向上策によって耐震裕度が増すとみなす。同向上策の有効性を評価するため、炉心損傷頻度CDFを指標に選び、CDFの低減を 地震PRAによって定量化する。崩壊熱除去機能喪失に至る事故シーケンスがナトリウム冷却高速炉SFRの地震時CDFに有意な寄与を示す。また、同事故シーケンスは超高温を経て炉心損傷に至る。本研究では過大地震時の振動への対策のみならず超高温での対策も評価するよう手法を考案した。手法の適用性を検討するため、ループ型SFRを想定して試計算を実施した。仮定した範囲内では、レジリエンス向上策は設計地震動の数倍の地震までCDFを有意に低減する効果を示した。適用性検討を通じて、有効性評価手法が開発された。

Engineering formulation of the irradiation growth behavior of zirconium-based alloys for light water reactors

垣内 一雄; 天谷 政樹; 宇田川 豊

Journal of Nuclear Materials, 573, p.154110_1 - 154110_7, 2023/01

https://doi.org/10.1016/j.jnucmat.2022.154110

The irradiation growth behavior of coupon specimens prepared from improved Zr-based alloys for light-water reactor fuel cladding, which have various additive elements and fabrication conditions, was investigated by conducting an irradiation test at 573 and 593 K under typical PWR coolant conditions up to a fast-neutron fluence of 7.810 (n/cm , E 1 MeV) in the Halden reactor in Norway. Based on the dimensional change data measured at interim and final inspections, the amounts of irradiation growth of the improved Zr-based alloys were formulated from the viewpoint of engineering. The trends of the parameters which express the effects of additive elements on irradiation growth behavior were in good agreement with those previously reported, and it was found that the amount of irradiation growth can be expressed by using a summation rule of the effect of each additive element on irradiation growth.

Irradiation growth behavior and effect of hydrogen absorption of Zr-based cladding alloys for PWR

垣内 一雄; 天谷 政樹; 宇田川 豊

Annals of Nuclear Energy, 171, p.109004_1 - 109004_9, 2022/06

https://doi.org/10.1016/j.anucene.2022.109004

In order to understand the dimensional stability of the fuel rod during long-term use in commercial LWRs, an irradiation growth testing in the Halden reactor of Norway was conducted on various fuel cladding materials including the improved Zr alloy. In this paper, the effect of hydrogen, which was absorbed in the cladding tube due to corrosion, on the irradiation growth behavior was evaluated. Comparison between the specimens with or without pre-charged hydrogen revealed that the effect of hydrogen absorption, accelerating irradiation growth, became significant when the hydrogen content exceeded the hydrogen solubility limit in the corresponding irradiation temperature. Analysis based on this understanding derived growth acceleration effect (0.060.01)%/100 ppm, whose denominator is defined as the amount of absorbed hydrogen involved in hydride precipitation under irradiation as a relevant parameter.

Irradiation growth behavior of improved Zr-based alloys for fuel cladding

天谷 政樹; 垣内 一雄; 三原 武

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.1048 - 1056, 2019/09

New fuel cladding alloys of which composition was changed from conventional ones have been developed by nuclear fuel vendors and utilities. Since the irradiation growth of fuel cladding is one of the most important parameters which determine the dimensional stability of fuel rod and/or fuel assembly during normal operation, the irradiation growth behavior of the improved Zr-based alloys for light-water reactor fuel cladding was investigated. The coupon specimens were prepared from fuel cladding tubes with various kinds of improved Zr-based alloys. The specimens were loaded into test rigs and had been irradiated in the Halden reactor in Norway under several coolant temperature conditions up to a fast-neutron fluence of 7.810 (n/cm, E 1 MeV). Irradiation conditions such as specimen temperatures had been continuously monitored during the irradiation. During and after the irradiation, the amount of irradiation growth of each specimen was evaluated as a part of the interim and final inspections. The effect of the difference in alloy composition on the amount of irradiation growth seemed insignificant if the other conditions e.g. the final heat treatment condition at fabrication and the irradiation temperature were the same.

Online chemical adsorption studies of Hg, Tl, and Pb on SiO and Au surfaces in preparation for chemical investigations on Cn, Nh, and Fl at TASCA

Lens, L.*; Yakushev, A.*; Dllmann, Ch. E.*; 浅井 雅人; Ballof, J.*; Block, M.*; David, H. M.*; Despotopulos, J.*; Di Nitto, A.*; Eberhardt, K.*; et al.

Radiochimica Acta, 106(12), p.949 - 962, 2018/12

AA2018-0417.pdf:0.99MB

https://doi.org/10.1515/ract-2017-2914

半減期449秒の短寿命同位体を用いて、水銀(Hg), タリウム(Tl), 鉛(Pb)の単一原子レベルでのSiO及びAu表面への固体吸着挙動をオンライン気相実験により調べた。超重元素Cn, Nh, Flの吸着エンタルピー測定のためのモデル実験として実施した。短寿命同位体はドイツ重イオン研究所の反跳核分離装置TASCAを用いて生成・分離した。生成核はヘリウムガス中に捕集された後、SiOあるいはAuで表面を覆われたSi検出器で作製されたガスクロマトグラフィーカラムへと導入した。短寿命Tl及びPb同位体は室温においてSiO表面に吸着し、Si検出器で測定することに成功した。一方、HgはSiO表面には吸着せず、Au表面に吸着した。この結果より、本実験のセットアップを用いることで短寿命Hg, Tl, Pb同位体の吸着特性を調べることができると証明され、この手法がCn, Nh, Flの実験にも適用できることが確認された。

中部日本東濃地域における珪長質火成岩類の記載岩石学データ

植木 忠正; 丹羽 正和

JAEA-Data/Code 2018-005, 94 Pages, 2018/08

JAEA-Data-Code-2018-005.pdf:15.6MB

山地の発達過程は、隆起量・侵食量に加え、動水勾配の変化に伴う地下水流動の長期的な変化にも影響を及ぼす要因となる。山地の隆起開始時期や発達過程を把握するための地質学的研究手法の一つとして、後背地解析がある。東濃地科学センターではこれまで、後背地を推定するための個別要素技術の整備を進めており、それらの適用性の確認として、中部日本東濃地域を対象とした事例研究を行ってきた。本報告書は、その事例研究の結果得られた基盤岩(珪長質火成岩類)の肉眼および顕微鏡下による岩石記載、および走査型X線分析顕微鏡による測定に基づく岩石表面の元素分布のデータを資料集として取りまとめたものである。

Polar rotor scattering as atomic-level origin of low mobility and thermal conductivity of perovskite CHNHPbI

Li, B.; 川北 至信; Liu, Y.*; Wang, M.*; 松浦 直人*; 柴田 薫; 河村 聖子; 山田 武*; Lin, S.*; 中島 健次; et al.

Nature Communications (Internet), 8, p.16086_1 - 16086_9, 2017/06

https://doi.org/10.1038/ncomms16086

Perovskite CHNHPbI exhibits outstanding photovoltaic performances, but the understanding of the atomic motions remains inadequate even though they take a fundamental role in transport properties. Here, we present a complete atomic dynamic picture consisting of molecular jumping rotational modes and phonons, which is established by carrying out high-resolution time-of-flight quasi-elastic and inelastic neutron scattering measurements in a wide energy window ranging from 0.0036 to 54 meV on a large single crystal sample, respectively. The ultrafast orientational disorder of molecular dipoles, activated at approximately 165 K, acts as an additional scattering source for optical phonons as well as for charge carriers. It is revealed that acoustic phonons dominate the thermal transport, rather than optical phonons due to sub-picosecond lifetimes. These microscopic insights provide a solid standing point, on which perovskite solar cells can be understood more accurately and their performances are perhaps further optimized.

A Remote-operated system to map radiation dose in the Fukushima Daiichi primary containment vessel

Nancekievill, M.*; Jones, A. R.*; Joyce, M. J.*; Lennox, B.*; Watson, S.*; 片倉 純一*; 奥村 啓介; 鎌田 創*; 加藤 道男*; 西村 和哉*

Proceedings of 5th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA 2017) (USB Flash Drive), 6 Pages, 2017/06

福島第一原子力発電所の原子炉内部のマッピングを目的とし、放射線検出器を組み合わせた潜水可能なROVシステムを開発している。線強度のマップを得るとともに放射性同位体を同定するため、CeBr無機シンチレータ検出器をROVに組み込んでいる。ROVは、直径約150mmの円筒形状で、自由度5で制御可能な5つのポンプを持つ2つのエンドキャップを備えている。CeBr検出器は、熱中性子束をマッピングすることが可能なLiホイルを有する単結晶化学蒸着中性子検出器で置き換えることが可能である。

Thermophysical properties of americium-containing barium plutonate

田中 康介; 佐藤 勇; 廣沢 孝志; 黒崎 健*; 牟田 浩明*; 山中 伸介*

Journal of Nuclear Science and Technology, 52(10), p.1285 - 1289, 2015/10

https://doi.org/10.1080/00223131.2015.1029554

BaPuAm)Oを調製し、ペロブスカイト型結晶構造を確認するとともに、音速測定により弾性率及びデバイ温度を求めた。また、熱伝導率を評価し、マトリクスと比較してきわめて小さい値を示すことがわかった。熱伝導率とデバイ温度の関係から、Ba系ペロブスカイト化合物の熱伝導率は原子間結合力の大きさで説明できることを明らかにした。