Thermodynamic Data to Model the Interaction Between Coolant and Fuel in Gen IV Sodium Cooled Fast Reactors
Creators
- Dinsdale, Alan1
- Gisby, John1
- Davies, Hugh1
- Konings, Rudy2
- Benes, Ondrej2
- Commissariat a l'energie atomique et aux energies alternatives - CEA (France)
- Aix-Marseille Universite, Jardin du Pharo, 58 bd Charles Livon, 13284 Marseille Cedex 07 (France)
- Studie Centrum voor Kernenergie/Centre d'etude de l'energie nucleaire - SCK.CEN, Boeretang 200, 2400, Mol (Belgium)
- IEEE Nuclear and Plasma Sciences Society - NPSS, New York (United States)
- 1. NPL, Teddington (United Kingdom)
- 2. European Commission, Joint Research Centre, Institute for Transuranic Elements, Karlsruhe (Germany)
Description
Understanding the behaviour of nuclear fuels in various environments is vital to the design and safe operation of nuclear reactors. While this is true if the reactor is operating within its design specification, it is even more so if accidents occur and the fuel is exposed to unexpected temperatures, pressures or chemical environments. It is clearly hazardous and costly to explore all such scenarios experimentally and therefore it is necessary to undertake modelling where possible using well-grounded theoretical approaches. This paper will show examples of where calculations of chemical and phase equilibria have been applied successfully to the long term storage of nuclear waste, phase formation during core meltdown and prediction of fission product release into the atmosphere. It will also highlight the development of thermodynamic data carried out during the European Metrology Research Project Metrofission required to model the potential interaction between the coolant, nuclear fuel, containment materials and atmosphere of a sodium cooled fast reactor. (authors)
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- ANIMMA--2013-1276
Conference
- Title
- 3. international conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications
- Acronym
- ANIMMA 2013
- Dates
- 23-27 Jun 2013
- Place
- Marseille (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 46071602
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; DESIGN; FISSION PRODUCT RELEASE; MELTDOWN; NUCLEAR FUELS; PHASE DIAGRAMS; RADIOACTIVE WASTES; SIMULATION; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; DIAGRAMS; ENERGY SOURCES; FUELS; INFORMATION; LIQUID METAL COOLED REACTORS; MATERIALS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; WASTES
Optional Information
- Notes
- 32 Refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/