Development of simulation tools for on-line reprocessing of the molten salt reactor concept
- 1. EDF R and D, Materials and Mechanics of Components Department, Moret sur Loing (France)
- 2. CEA Cadarache, Nuclear Energy Division/DTN/STPA/LPC, Saint Paul Lez Durance (France)
Description
In the frame of the Generation IV International Forum, Molten Salt Reactor (MSR) has been selected as a promising technology. Nevertheless, important work remains to be done to demonstrate the feasibility of the on line reprocessing unit. We have also to develop a simulation tool that integers both the reactor part of the concept as well as the reprocessing plant. To reach this goal, we chose a two stage development plan. First stage is the development of a general architecture for the simulation tool of the reprocessing unit. A first and very simple version has been developed, with the aim to test the different options for the reprocessing unit. In a second stage, we launch an important program to develop simulation tools able to simulate the main pyrochemical operations. In this work, we developed a database on the solubility of actinides and lanthanides in liquid metals and a preliminary version of a simulation tool, able to calculate the evolution of the molten salt phase and the liquid metal phase in a electroreduction on liquid cathode. First results are given and discussed using Al liquid cathode. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability
- Imprint Pagination
- [2562 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International conference on nuclear energy systems for future generation and global sustainability
- Acronym
- GLOBAL 2005
- Dates
- 9-13 Oct 2005
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37048859
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; COMPUTERIZED SIMULATION; DATA BASE MANAGEMENT; ELECTROLYSIS; FUEL REPROCESSING PLANTS; LIQUID METALS; MEETINGS; MOLTEN SALT REACTORS; ON-LINE SYSTEMS; PYROCHEMICAL REPROCESSING; PYROMETALLURGY; RARE EARTHS; SOLUBILITY
- Descriptors DEC
- ELEMENTS; EXTRACTIVE METALLURGY; FLUIDS; LIQUIDS; LYSIS; MANAGEMENT; METALLURGY; METALS; NUCLEAR FACILITIES; REACTORS; REPROCESSING; SEPARATION PROCESSES; SIMULATION
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name GL1XX, Paper ID GL133DF.pdf; 4 refs., 7 figs., 2 tabs.