Fast Code System: Review of Recent Applications
Creators
- 1. Paul Scherrer Institut, Villigen (Switzerland)
- 2. École Polytechnique Fédérale de Lausanne (Switzerland)
- 3. Eidgenössische Technische Hochschule Zürich (Switzerland)
Description
The FAST code system, consisting of coupled neutronics (ERANOS and SERPENT), thermal-hydraulic (TRACE) and fuel behaviour (FRED) modules, is currently being developed and used at Paul Scherrer Institut for static and transient analysis of different innovative fast reactors. The paper presents the review of few recent studies in which the FAST code system was used for: 1) validation of static neutronic modeling using data of PHENIX EOL control rod shift test and BFS-62-3A critical test; 2) validation of coupled neutron kinetics and system thermal hydraulics using data of PHENIX EOL natural circulation test; 3) for different fast reactor concepts: comparison of closed fuel cycles; 4) nuclear data uncertainty propagation in dynamic calculations; 5) the SFR core behaviour under unprotected loss-of-flow conditions. (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
- 10 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
- 46091198
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CONTROL ELEMENTS; FAST REACTORS; FUEL CYCLE; LOSS OF FLOW; NATURAL CONVECTION; REVIEWS; THERMAL HYDRAULICS; TRANSIENTS; VALIDATION
- Descriptors DEC
- ACCIDENTS; CONVECTION; DOCUMENT TYPES; ENERGY TRANSFER; EPITHERMAL REACTORS; EVALUATION; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TESTING
Optional Information
- Notes
- 23 refs., 11 figs., 3 tabs.
- Secondary number(s)
- IAEA-CN--199/156