Applicability Evaluation of the In-can Vitrification to Fukushima Waste - 19016
Creators
- 1. Commissariat a l'energie Atomique (CEA), Nuclear Energy Division, Enrichment, Decommissioning and Waste Research Department, CEA, DEN/DE2D, BP 17171 - 30207 Bagnols-sur-Ceze Cedex (France)
- 2. Orano Cycle, Tour AREVA, 1 place Jean Millier, 92084 Paris La Defense (France)
- 3. ANADEC, 1201 Takada, Kashiwa-shi, Chiba-ken, 277-0861 (Japan)
Description
The in-can vitrification process has been developed by the CEA for an internal application (alpha waste treatment) since 2005 and can be rated TRL 7. On these basis the DEM'n'MELT consortium which gathers Orano, CEA and ECM technologies is currently developing and qualifying a robust, simple and versatile in situ vitrification process dedicated to D and D waste. The DEM'n'MELT vitrification process is developed with a modular design, the main characteristics are presented hereafter: - Suitable for high or medium level waste. - Heated by a simple and robust resistance furnace. - Offering homogeneity to the melted mixture. - Suitable for solid or liquid wastes, including zeolites and sludge. - Flexible enough to accommodate uncertainties on waste composition. - Designed in order to produce a small amount of secondary waste. - Implementing proven technological solutions from French high level vitrification shops. - Requiring low investment and operation costs. Regarding this features, the in-can process has been deemed as an appropriate tool for the vitrification of the Fukushima water treatment secondary waste (mineral adsorbants, sludge). The evaluation of the In-can process for Fukushima waste is a project led by Orano, CEA and ANADEC. The main phases are: - Scenarios and glass formulation studies to optimize waste loading and matrix homogeneity. - Bench scale tests on several scenarios of blended waste. - Pilot scale test on one selected scenario (reference scenario). - Feasibility evaluation to Fukushima Daiichi Nuclear Power Station implementation. This paper presents the first results of this project with a highlighting on glass waste loading, glass properties, bench tests and pilot test results, process parameters, and material balance. (authors)
Availability note (English)
Available from: WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (US)Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- INIS-US--21-WM-19016
Conference
- Title
- 45. Annual Waste Management Conference
- Acronym
- WM2019
- Dates
- 3-7 Mar 2019
- Place
- Phoenix, AZ (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52043188
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CEA; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; IMPLEMENTATION; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; LIQUID WASTES; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE STORAGE; VITRIFICATION; WASTE PROCESSING; WATER TREATMENT; ZEOLITES
- Descriptors DEC
- FRENCH ORGANIZATIONS; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MANAGEMENT; MATERIALS; MINERALS; NATIONAL ORGANIZATIONS; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; REACTOR SITES; SILICATE MINERALS; STORAGE; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE STORAGE; WASTES
Optional Information
- Notes
- available online at: https://www.xcdsystem.com/wmsym/2019/index.html