Relevant bibliographies by topics / Pyrochemical treatment

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  1. Journal articles
  2. Dissertations / Theses
  3. Book chapters
  4. Conference papers

Academic literature on the topic 'Pyrochemical treatment'

Author: Grafiati
Published: 31 May 2025
Last updated: 31 July 2025

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Journal articles on the topic "Pyrochemical treatment"

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Hayashi, Hirokazu, Takumi Sato, Hiroki Shibata, Masaki Kurata, Takashi Iwai, and Yasuo Arai. "Pyrochemical treatment of spent nitride fuels for MA transmutation." Science China Chemistry 57, no. 11 (2014): 1427–31. http://dx.doi.org/10.1007/s11426-014-5205-9.

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Harrison, M. T., and D. McKendrick. "Treatment of waste salt arising from the pyrochemical treatment of used nuclear fuel using precipitation methods." MRS Advances 7, no. 5-6 (2022): 117–21. http://dx.doi.org/10.1557/s43580-022-00244-z.

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Krachler, Michael, Rafael Alvarez-Sarandes, Pavel Souček, and Paul Carbol. "High resolution ICP-OES analysis of neptunium-237 in samples from pyrochemical treatment of spent nuclear fuel." Microchemical Journal 117 (November 2014): 225–32. http://dx.doi.org/10.1016/j.microc.2014.07.005.

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Gilbert, M. R. "Pressureless Sintering of Sodalite Waste-forms for the Immobilization of Pyroprocessing Wastes." MRS Proceedings 1744 (2015): 61–66. http://dx.doi.org/10.1557/opl.2015.394.

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ABSTRACTSodalite (Na8[AlSiO4]6Cl2), a naturally occurring Cl-containing mineral, has long been regarded as a potential immobilization matrix for the chloride salt wastes arising from pyrochemical reprocessing operations, as it allows for the conditioning of the waste salt as a whole without the need for any pre-treatment. Here the consolidation and densification of Sm-doped sodalite (as an analogue for AnCl3) has been investigated with the aim of producing fully dense (i.e. > 95 % t.d.) ceramic monoliths via conventional cold-press-and-sinter techniques at temperatures of < 1000 °C. Micr
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N., K. MITRA, DAS D., SEN ALOKE, and BASUMAJUMDAR A. "Influence of Exchangeable Cations on DTA Characteristics of Kaolinite and Montmorillonite Clays." Journal of Indian Chemical Society Vol. 62, Sep 1985 (1985): 662–65. https://doi.org/10.5281/zenodo.6322175.

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&nbsp;Department of Chemical Technology, University of Calcutta, Calcutta-700 009<strong> </strong> <em>Manuscript received 28 August 1984, revised 7 May 1985, accepted 11 September 1985</em> The influence of exchangeable cations in the structure of kaolinite and mont&shy;morillonite minerals on the phase transformation on progressive heat treatment, has been studied through DTA curves. Hydration energy of the cations influences the expulsion of water from the clay lattice. The high temperature phase conversions were also influenced catalytically by exchangeable cations.&nbsp;
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KOTANI, Masaki, and Shinji OGIHARA. "Effects of pyrochemical treatment for producing interfacial carbon layer on tensile properties of PIP-processed SiC/SiC composites." Proceedings of the Materials and processing conference 2019.27 (2019): 422. http://dx.doi.org/10.1299/jsmemp.2019.27.422.

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Rodrigues, Davide, Gabriela Durán-Klie, and Sylvie Delpech. "Pyrochemical reprocessing of molten salt fast reactor fuel: focus on the reductive extraction step." Nukleonika 60, no. 4 (2015): 907–14. http://dx.doi.org/10.1515/nuka-2015-0153.

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Abstract The nuclear fuel reprocessing is a prerequisite for nuclear energy to be a clean and sustainable energy. In the case of the molten salt reactor containing a liquid fuel, pyrometallurgical way is an obvious way. The method for treatment of the liquid fuel is divided into two parts. In-situ injection of helium gas into the fuel leads to extract the gaseous fission products and a part of the noble metals. The second part of the reprocessing is performed by ‘batch’. It aims to recover the fissile material and to separate the minor actinides from fission products. The reprocessing involves
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Kotani, Masaki, and Shinji Ogihara. "Effects of pyrochemical treatment for producing interfacial carbon layer on tensile properties of polymer-derived-matrix-based SiC/SiC composites." Journal of Asian Ceramic Societies 9, no. 2 (2021): 519–30. http://dx.doi.org/10.1080/21870764.2021.1896095.

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Martinot, L., and M. Ligot. "The potential/pO2− diagrams of uranium and the feasibility of a pyrochemical head-end treatment of nuclear fuels in molten chlorides." Journal of Radioanalytical and Nuclear Chemistry Letters 136, no. 1 (1989): 53–60. http://dx.doi.org/10.1007/bf02165086.

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Gonzalez, M., L. Hansen, D. Rappleye, R. Cumberland, and M. F. Simpson. "Application of a One-Dimensional Transient Electrorefiner Model to Predict Partitioning of Plutonium from Curium in a Pyrochemical Spent Fuel Treatment Process." Nuclear Technology 192, no. 2 (2015): 165–71. http://dx.doi.org/10.13182/nt15-28.

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Dissertations / Theses on the topic "Pyrochemical treatment"

1

Costantine, Joelle. "Chimie des sels chlorures fondus pour les concepts de réacteur nucléaire à sels fondus." Electronic Thesis or Diss., université Paris-Saclay, 2025. http://www.theses.fr/2025UPASP017.

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Les réacteurs nucléaires à sels fondus (RSF) sont parmi les six concepts sélectionnés par le Forum International Génération IV (GenIV) pour le développement des réacteurs nucléaires de quatrième génération. La spécificité des RSF réside dans l'utilisation d’un combustible liquide constitué d’un sel fondu. Ce type de concept répond aux objectifs de GenIV en termes de sureté, durabilité et minimisation des déchets ultimes. En effet, l’utilisation d’un combustible liquide apporte une sureté intrinsèque au réacteur car lors d’une augmentation de la température, le sel se dilate ce qui stoppe la ré
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Book chapters on the topic "Pyrochemical treatment"

1

Koyama, T. "Nuclear engineering for pyrochemical treatment of spent nuclear fuels." In Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment. Elsevier, 2011. http://dx.doi.org/10.1533/9780857092274.3.269.

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Conference papers on the topic "Pyrochemical treatment"

1

Kofuji, Hirohide, Tetsuji Yano, Munetaka Myochin, Kanae Matsuyama, Takeshi Okita, and Shinya Miyamoto. "Optimization of Chemical Composition in the Iron Phosphate Glass as the Matrix of High Level Waste Generated From Pyroprocessing." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30688.

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As part of ongoing research and development of nuclear waste disposal techniques suitable for the pyrochemical processing system [1], iron-phosphate glass was examined as an alternative waste form for high level waste generated from the electro-refining process [2]. To enhance the waste element content in the glass matrix and improve the durability of the waste form, optimization experiments of the glass composition were performed, and the effects of other additional transition metal oxides were determined. From the surface analysis of iron phosphate glass, a leaching mechanism was assumed for
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Bateman, K. J., B. R. Westphal, and M. A. Stawicki. "Experimental Equipment Design and Testing of the DEOX Process." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49451.

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Several technologies exist or are under development for treating spent oxide nuclear fuels. Foremost among these are aqueous and pyrochemical reprocessing which both involve a head-end fuel dissolution step. This dissolution step may potentially be shortened if it is combined with a fuel decladding and size reduction process. Declad and Oxidize (DEOX), an advanced head-end processing concept, is being assessed at Argonne National Laboratory to meet these decladding and size reduction needs via the oxidation of UO2 to U3O8. This work is being done in collaboration with Oak Ridge National Labora
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Journal articles
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