Published October 2005
| Version v1
Journal article
FAST: An advanced code system for fast reactor transient analysis
Creators
- 1. Laboratory for Reactor Physics and Systems Behaviour, Paul Scherrer Institute, 5232 Villigen PSI (Switzerland)
Description
One of the main goals of the FAST project at PSI is to establish a unique analytical code capability for the core and safety analysis of advanced critical (and sub-critical) fast-spectrum systems for a wide range of different coolants. Both static and transient core physics, as well as the behaviour and safety of the power plant as a whole, are studied. The paper discusses the structure of the code system, including the organisation of the interfaces and data exchange. Examples of validation and application of the individual programs, as well as of the complete code system, are provided using studies carried out within the context of designs for experimental accelerator-driven, fast-spectrum systems
Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2005.06.002;
- PII
- S0306-4549(05)00149-0;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 32
- Journal Issue
- 15
- Journal Page Range
- p. 1613-1631
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37036233
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCELERATORS; COOLANTS; DESIGN; FAST REACTORS; NUCLEAR POWER PLANTS; SAFETY; SAFETY ANALYSIS; SPECTRA; TRANSIENTS; VALIDATION
- Descriptors DEC
- EPITHERMAL REACTORS; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; TESTING; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.