不飽和圧縮ベントナイト中での塩水浸潤挙動データの取得

佐藤 久*; 高山 裕介; 鈴木 英明*; 佐藤 大介*

JAEA-Data/Code 2023-010, 47 Pages, 2023/09

JAEA-Data-Code-2023-010.pdf:1.45MB

高レベル放射性廃棄物の処分場を沿岸部に建設した場合、沿岸部の地下水は海水の影響を受けて塩濃度が高くなるため、海水系の地下水が緩衝材を含む人工バリアに与える影響を十分に考慮して評価する必要がある。本報告では、緩衝材が飽和に至るまでの過渡的な期間において、海水系の地下水が緩衝材中での水分や溶質の移行現象に与える影響を評価することを目的として、異なる乾燥密度の圧縮ベントナイト試料を対象に、浸潤水のNaCl濃度を変えた一次元の塩水浸潤試験を実施し、浸潤水のNaCl濃度と浸潤速度の関係や浸潤試験後の圧縮ベントナイト試料中の含水比分布データを取得した。また、浸潤試験後の試料中の塩化物イオンの濃度分布を分析することにより、不飽和な圧縮ベントナイト中での溶質の移行挙動の理解に資するデータを取得した。その結果、浸潤水のNaCl濃度が高くなるに従い浸潤は速くなり、乾燥密度1.4Mg/mから1.8Mg/m、浸潤水のNaCl濃度が0(蒸留水)から4.0mol/dmまでの範囲において、浸潤時間と浸潤量の関係は浸潤水の拡散現象とみなして評価できることが確認された。また、浸潤水が蒸留水の場合、含水比は給水側から浸潤距離に応じてなだらかに低下する分布となるが、浸潤水がNaCl水溶液の場合、含水比は給水側から浸潤の先端近くまで比較的高い状態を保ちながら浸潤の先端で低下する分布となり、NaCl濃度が高くなるに従いその傾向が強くなることが確認された。浸潤試験後試料の塩化物イオン濃度の分析結果から、給水側よりも浸潤方向側の領域で給水側より塩化物イオンの濃度が部分的に高くなる現象(塩化物イオンの濃縮)が起きており、この傾向は供試体の乾燥密度が低くなるに従い強くなることや、浸潤水のNaCl濃度が高くなるに従い強くなることが確認された。また、浸潤に伴い塩化物イオンが濃縮する現象は供試体の初期含水比に依存することが確認されており、浸潤に伴う塩化物イオンの濃縮が生じない条件を設定可能な見通しが得られた。

Angular momentum transfer in multinucleon transfer channels of O + Np

田中 翔也*; 廣瀬 健太郎; 西尾 勝久; Kean, K. R.*; 牧井 宏之; Orlandi, R.; 塚田 和明; 有友 嘉浩*

Physical Review C, 105(2), p.L021602_1 - L021602_5, 2022/02

https://doi.org/10.1103/PhysRevC.105.L021602

The angular momentum of a primary excited compound nucleus produced in multinucleon transfer reaction is an important quantity to evaluate cross sections to synthesize neutron-rich heavy element nuclei as well as for surrogate reaction studies. The mechanism is, however, not enough understood due to the lack of detailed experimental data. In the present study, we determined the angular momentum of primary excited nuclei, Np, Pu, and Am, produced in the multi-nucleon transfer channels of the O + Np reaction. With this aim, angular distributions of fission fragments with respect to the axis perpendicular to the reaction plane were measured for each compound nucleus. The distributions show an anisotropy exhibiting an enhanced yield on the reaction plane. They are well reproduced by a saddle point model, from which the average angular momentum is derived in the model framework. The angular momentum increases with the compound-nucleus mass, thus the number of nucleons exchanged, but shows a saturating trend toward heavier compound nuclei. These results are the first ones to point to the dependence of the angular momentum on the transfer channels.

和歌山県田辺市本宮町川湯温泉周辺の露頭の赤外線画像

島田 耕史; 後藤 翠; 丹羽 正和; 下茂 道人*

地質学雑誌, 127(10), p.I - II, 2021/10

AA2021-0095.pdf:1.35MB

https://doi.org/10.5575/geosoc.2021.0021

地下からの高温流体(液体・気体)の継続的な滲出地点は、赤外線画像により簡便に把握できるであろう。このことを、川沿いに自然湧出する川湯温泉の露頭において、赤外線画像と可視光画像が同時に得られるFLIR社製、C5カメラにより確かめた画像を紹介する。川岸や川底から湧出する温泉による露頭や水面の温度上昇、温泉とともに高濃度メタンを含む気体が滲出する割れ目周辺の岩の温度上昇、冬季に川をせき止めて作られる仙人風呂の土手造成により、この割れ目が流体通路として機能しなくなった様子が一目で確認できる。赤外線画像は、地下からの高温流体の滲出地点の迅速把握に有効な場合がある。

Overview of environmental impact assessment studies on radioactive contamination after the Fukushima Daiichi Nuclear Power Plant accident

飯島 和毅; 林 誠二*; 玉置 雅紀*

Global Environmental Research (Internet), 24(2), p.85 - 93, 2021/06

福島第一原子力発電所事故による環境の放射性物質による汚染は、事故から約10年が経過する間に明らかに減少している。しかし、除染されていない森林に起因すると思われる自然生態系の汚染の長期化が多くの研究で指摘されており、生物学的に利用可能な放射性セシウムの環境動態とその生態系への移行については、より詳細な調査が必要と考えられた。また、生物への放射線の影響については、特に福島の避難地域では、放射線による直接的な影響よりも野生生物への避難の影響が顕著であった。

総合討論; 環境移行パラメータのデータベース化と生活圏被ばく線量評価への活用

高橋 知之*; 内田 滋夫*; 武田 聖司; 中居 邦浩*

KURNS-EKR-11, p.97 - 102, 2021/03

https://www.rri.kyoto-u.ac.jp/PUB/report/09_kurns/temp/kurns-ekr-011.pdf

農作物や水産物への元素の移行係数等の生活圏環境移行パラメータに対するIAEAのデータベースの取りまとめ状況や、わが国における放射性廃棄物処分の被ばく線量評価におけるデータベースの活用の状況について概説するとともに、将来の具体的な放射性廃棄物処分の地域における被ばく線量評価を想定した場合に対し、今後の生活圏環境移行パラメータのデータベース構築に必要な戦略、整備されるべき観点、課題点等に関して、専門家の意見と総合討論の結果について取りまとめた。

Measurement of fission-fragment mass distributions in the multinucleon transfer channels of the O+Np reaction

Vermeulen, M. J.; 西尾 勝久; 廣瀬 健太郎; Kean, K. R.; 牧井 宏之; Orlandi, R.; 塚田 和明; Tsekhanovich, I.*; Andreyev, A. N.; 石崎 翔馬*; et al.

Physical Review C, 102(5), p.054610_1 - 054610_11, 2020/11

https://doi.org/10.1103/PhysRevC.102.054610

Fission fragment mass distributions for 23 nuclei (U, Np, Pu, Am, Cm, and Bk) were measured using the multi-nucleon transfer approach in the reaction of O+Np, and their excitation-energy dependence was obtained up to a maximum of 70 MeV. Among them, the low energy fission of Np, Pu, and Cm is reported for the first time. The experimental data for all the studied nuclei were compared to the Langevin calculations. The calculation which takes into account the effects of multi-chance fission well reproduced the peak-to-valley ratio and mass-asymmetric peak positions of the distributions. The angular momenta given to the fissioning nucleus is also discussed.

Development of experimental technology for simulated fuel-assembly heating to address core-material-relocation behavior during severe accident

阿部 雄太; 山下 拓哉; 佐藤 一憲; 中桐 俊男; 石見 明洋

Journal of Nuclear Engineering and Radiation Science, 6(2), p.021113_1 - 021113_9, 2020/04

https://doi.org/10.1115/1.4045450

The authors are developing an experimental technology for simulating severe accident (SA) conditions using simulate fuel material (ZrO) that would contribute, not only to Fukushima Daiichi (1F) decommissioning, but also to enhance the safety of worldwide existing and future nuclear power plants through clarification of accident progression behavior. Nontransfer (NTR) type plasma, which has been in practical use with a large torch capacity as high as 2 MW, has the potential to heat subject materials to very high temperatures without selecting the target to be heated. When simulating 1F with SA code, the target of this core-material-melting and relocation (CMMR) experiment was to confirm that NTR plasma has a sufficient heating performance realizing large temperature gradients ( 2000 K/m) expected under 1F conditions. The authors selected NTR-type plasma-heating technology that has the advantage of continuous heating in addition to its high-temperature level. The CMMR-2 experiments were carried out in 2017 applying the improved technology (higher heating power and controlled oxygen concentration). The CMMR-2 experiment adopted a 30-min heating period, wherein the power was increased to a level where a large temperature gradient was expected at the lower part of the core under actual 1F accident conditions. Most of the control blade and channel box migrated from the original position. After heating, the simulated fuel assembly was measured by X-ray computed tomography (CT) technology and by electron probe micro-analyzer (EPMA). CT pictures and elemental mapping demonstrated its excellent performance with rather good precision. Based on these results, an excellent perspective, in terms of applicability of the NTR-type plasma-heating technology to the SA experimental study, was obtained.

Validation of the multinucleon transfer method for the determination of the fission barrier height

Kean, K. R.; 西尾 勝久; 廣瀬 健太郎; Vermeulen, M. J.; 牧井 宏之; Orlandi, R.; 塚田 和明; Andreyev, A. N.; Tsekhanovich, I.*; 千葉 敏*

Physical Review C, 100(1), p.014611_1 - 014611_6, 2019/07

https://doi.org/10.1103/PhysRevC.100.014611

The validity of the multinucleon transfer (MNT) approach for deduction of fission barrier heights was investigated in an experiment carried out at the JAEA tandem accelerator facility. By using the O+Np reaction, fission barrier heights were inferred from fission probabilities of the nuclei Np and Pu produced in the and transfer channels, respectively. The deduced values of fission barriers agree well with the literature data, thus demonstrating the potential of the MNT reactions for obtaining fission-barrier data for nuclei not accessible for fission studies via neutron- or light charged particle-induced reactions.

Development of experimental technology for simulated fuel-assembly heating to address core-material-relocation behavior during severe accident

阿部 雄太; 山下 拓哉; 佐藤 一憲; 中桐 俊男; 石見 明洋; 永江 勇二

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 9 Pages, 2018/07

https://asme.pinetec.com/icone26/

Authors are developing an experimental technology to realize experiments simulating Severe Accident (SA) conditions using simulant fuel material (ZrO with slight addition of MgO for stabilization) that would contribute not only to Fukushima Daiichi (1F) decommissioning but also to enhance the safety of worldwide existing and future nuclear power plants through clarification of the accident progression behavior. Based on the results of the prototype test, improvement of plasma heating technology was conducted. The Core Material Melting and Relocation (CMMR)-1/-2 experiments were carried out in 2017 with the large-scale simulated fuel assembly (1 m 0.3 m ) applying the improved technology (higher heating power and controlled oxygen concentration). In these two tests, heating history was different resulting basically in similar physical responses with more pronounced material melting and relocation in the CMMR-2 experiment. The CMMR-2 experiment is selected here from the viewpoint of establishing an experimental technology. The CMMR-2 experiment adopted 30-min heating period, the power was increased up to a level so that a large temperature gradient ( 2,000 K/m) expected at the lower part of the core in the actual 1F accident conditions. Most of the control blade and the channel box migrated from the original position. After the heating, the simulated fuel assembly was measured by the X-ray Computed Tomography (CT) technology and by Electron Probe Micro Analyzer (EPMA). CT pictures and elemental mapping demonstrated its excellent performance with rather good precision. Based on these results, an excellent perspective in terms of applicability of the non-transfer type plasma heating technology to the SA experimental study was obtained.

Release and transport behaviors of non-gamma-emitting fission products and actinides in steam and hydrogen atmospheres

三輪 周平; Ducros, G.*; Hanus, E.*; Bottomley, P. D. W.*; Van Winckel, S.*; 逢坂 正彦

Nuclear Engineering and Design, 326, p.143 - 149, 2018/01

https://doi.org/10.1016/j.nucengdes.2017.11.017

水蒸気及び水素雰囲気下での非線放出核種の核分裂生成物(FP)及びアクチニド13核種の放出移行挙動を、FP放出移行実験VERCORSにおける沈着物の化学分析結果に基づいて評価した。化学平衡計算による化学形態を考慮して放出移行挙動を評価した結果、ストロンチウムの放出は水素雰囲気で促進され、一部は低温領域まで移行していくこと、ウランの放出は水蒸気雰囲気で促進される一方で、高温領域に留まること等、新規な知見を得た。