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Journeau, C.*; Delacroix, J.*; Gu
var, C.*; Testud, V.*; Brackx, E.*; Porcheron, E.*; Bouland, A.*; Berlemont, R.*; 池田 篤史
Science Talks (Internet), 6, p.100215_1 - 100215_9, 2023/05
One of the important challenges for the decommissioning of the damaged reactors of the Fukushima Daiichi Nuclear Power Station (1F) is the fuel debris retrieval. The URASOL (URAnium and aeroSOL) project has been undertaken by the French consortium laboratories consisting of ONET, CEA, and IRSN for JAEA. It aims at acquiring basic data on the generation and characteristics of radioactive aerosols from the thermal or mechanical processing of fuel debris simulant. Prototypic fuel debris samples were fabricated based on the average of the lower head compositions computed in the OECD/BSAF benchmark. Samples were heated in an induction furnace to simulate thermal cutting and released aerosols were collected during three temperature ramps using impactors. The collected aerosols were chemically analyzed by ICP-AES and ICP-MS. Iron and tin are the major elements found in these aerosols, followed by chromium and silicon. Significant releases of tellurium, barium and cerium were observed.
Brissonneau, L.*; 池内 宏知; Piluso, P.*; Gousseau, J.*; David, C.*; Testud, V.*; Roger, J.*; Bouyer, V.*; 北垣 徹; 仲吉 彬; et al.
Journal of Nuclear Materials, 528, p.151860_1 - 151860_18, 2020/01
被引用回数：17 パーセンタイル：87.08(Materials Science, Multidisciplinary)In the framework of JAEA-CEA collaboration, experimental studies have been conducted for estimating the material characteristics of corium debris representative of the Fukushima Daiichi nuclear damaged plants. A test has been performed in the VULCANO facility in CEA Cadarache to simulate the concrete corium interaction (CCI) with prototypic corium (using depleted uranium) and concrete of Fukushima Daiichi 1F1 Nuclear Plant. This paper presents the Post Test Analyses on 9 samples representative of the CCI during this test: in the corium pool, in the crusts and at the vertical and horizontal interfaces with the concrete. Analyses have been performed by SEM/EDS, X-Ray Diffraction, complete dissolution and ICP, micro-hardness measurements of the main phases. The major phases encountered are uranium rich and zirconium rich oxides forming nodules from micrometers to millimeters size, chromium-iron rich precipitates of several micrometers, metallic Fe-Ni droplets and chromium-silicon rich filaments in a matrix, likely vitreous, rich in concrete elements: Si, Al, Ca, but containing up to 12 cations. The matrix is the softer oxide phase, when the Cr rich precipitates are the harder. The analyses are consistent with the estimated macroscopic ablation ratio, but do not still explain the important axial ablation observed for this specific basaltic concrete. The different phases formation, distribution and solidification path are discussed. First comparisons are proposed with the former CCI tests with European concretes. These results give helpful insights for the future dismantling of the plant and for a deeper understanding of the CCI process for basaltic concrete.
仲吉 彬; 池内 宏知; 北垣 徹; 鷲谷 忠博; Bouyer, V.*; Journeau, C.*; Piluso, P.*; Excoffier, E.*; David, C.*; Testud, V.*
Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet), 4 Pages, 2019/05
A large-scale Molten Core-Concrete Interaction (MCCI) test (VF-U1) under the Fukushima Daiichi Nuclear Power Station (1F) conditions (core material composition, concrete, and decay heat) was conducted at the large MCCI test facility (VULCANO) owned by French Alternative Energies and Atomic Energy Commission (CEA) in France. About 50 kg of simulated debris was melted and brought into contact with concrete to erode concrete under 1F conditions. After cooling, the concrete test section (concrete and MCCI product) was dismantled. Main observations of the structure of solidified pool (crust, porosity, oxide/metal layer, etc.) and of the ablation are given. The technical results obtained herein are summarized, and they provide interesting knowledge that will help with the decommissioning of 1F.
Guvar, C.*; Faure, J.*; Testud, V.*; Roger, J.*; Domenger, R.*; Valette, R.*; Brackx, E.*; Bouyer, V.*; Journeau, C.*; Berlemont, R.*; et al.
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URASOLとダスト飛散率プロジェクトは、それぞれJAEAとCRIEPIがONET/CEA/IRSNと共同で主導し、熱または機械工具で切断された劣化ウラン酸化物を含む模擬燃料デブリからエアロゾルの生成と特性に関する基礎データを取得することを目的とする。ONET/CEA/IRSNが開発したプロセス全体では、模擬燃料デブリの仕込み組成決定と製作、切断用試料の準備、切断試験とオンラインでのエアロゾル測定、エアロゾルのサンプリング、模擬燃料デブリ製作時とエアロゾル生成試験後分析を実施可能である。本発表では、模擬燃料デブリ(Ex-Vessel組成のVF-U3)の製作時、及びそれらの加工時のエアロゾルの化学および微細構造分析に焦点を当てる。
