Comparison of Results of SAS-SFR Calculations of the CP-ESFR Working Horse and Optimized Core Designs during the Initial Phase of an ULOF Accident
- 1. Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Karlsruhe (Germany)
Description
Simulations using the code SAS-SFR were performed to assess the behaviour of two core designs investigated within the European Collaborative Project CP-ESFR. The results for an unprotected loss of flow (ULOF) accident in the initiation phase are presented and analysed for the Working Horse and Optimized Oxide core designs under Beginning-Of-Life (BOL) conditions. The core geometry has to be represented according to simulation capabilities of the SAS-SFR code. The values for the spatial distributions of material worth (sodium, fuel, and steel) and Doppler coefficient were calculated with the modular code system KANEXT using the JEFF 3.1.1 cross section data library. The cores are compared regarding the design optimization related to the consequences of severe accidents. For the optimized core design, the grace time rises considerably and the power excursion is milder. It is a step in the right direction, but not yet sufficient to prevent core destruction. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-104114-2
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). COMPANION CD-ROM. Proceedings of an International Conference
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 9 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios
- Acronym
- FR13
- Dates
- 4-7 Mar 2013
- Place
- Paris (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46091103
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CROSS SECTIONS; DESIGN; DOPPLER COEFFICIENT; EXCURSIONS; LOSS OF FLOW; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; OXIDES; SIMULATION; SODIUM; SPATIAL DISTRIBUTION; STEELS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; DISTRIBUTION; ELEMENTS; ENERGY SOURCES; FUELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; METALS; OXYGEN COMPOUNDS; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTOR MATERIALS; TRANSITION ELEMENT ALLOYS
Optional Information
- Contract/Grant/Project number
- Contract 232658
- Notes
- 4 refs., 6 figs., 5 tabs.
- Secondary number(s)
- IAEA-CN--199/320