Published April 2015 | Version v1
Book

Fast Code System: Review of Recent Applications

  • 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)

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
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