Tailoring the response of Autonomous Reactivity Control (ARC) systems
Creators
- 1. Department of Nuclear Engineering, University of California Berkeley (United States)
- 2. Department of Physics and Astronomy, Uppsala University, Uppsala (Sweden)
- 3. General Electric Advanced Reactor Systems Department (retired), Sunnyvale, CA (United States)
- 4. Nuclear Engineering Division, Argonne National Laboratory, IL (United States)
Description
Highlights: • ARC-systems can provide inherent safety in all types of fast reactors. • Oscillatory behavior in ULOF events can be avoided by careful design. • Time-delay of ARC system response is minimized using an annular upper reservoir. • The methods to determine required reactivity worth for ARC systems are presented. - Abstract: The Autonomous Reactivity Control (ARC) system was developed to ensure inherent safety of Generation-IV reactors while having a minimal impact on reactor performance and economic viability. In this study we present the transient response of fast reactor cores to postulated accident scenarios with and without ARC systems installed. Using a combination of analytical methods and numerical simulation, the principles of ARC system design that assure stability and avoids oscillatory behavior have been identified. A comprehensive transient analysis study for ARC-equipped cores, including a series of Unprotected Loss of Flow (ULOF) and Unprotected Loss of Heat Sink (ULOHS) simulations, were performed for Argonne National Laboratory (ANL) Advanced Burner Reactor (ABR) designs. With carefully designed ARC-systems installed in the fuel assemblies, the cores exhibit a smooth non-oscillatory transition to stabilization at acceptable temperatures following all postulated transients. To avoid oscillations in power and temperature, the reactivity introduced per degree of temperature change in the ARC system needs to be kept below a certain threshold the value of which is system dependent, the temperature span of actuation needs to be as large as possible.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.09.036Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.09.036;
- PII
- S0306-4549(16)30501-1;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 99
- Journal Page Range
- p. 383-398
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48085476
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANL; ATWS; COMPUTERIZED SIMULATION; CONTROL; DESIGN; FAST REACTORS; FUEL ASSEMBLIES; LOSS OF FLOW; REACTIVITY WORTHS; REACTOR CORES; REACTOR SAFETY; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; EPITHERMAL REACTORS; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.