Published April 2015 | Version v1
Book

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)

Part of:
Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). COMPANION CD-ROM. Proceedings of an International Conference

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