Innovative Control Strategy for the Fast-Runback Transient in a Sodium-Cooled Small Modular Reactor - 14139
Creators
- 1. Politecnico di Milano, Department of Energy, CeSNEF-Nuclear Engineering Division, via Ponzio 34/3, 20133 Milano (Italy)
- 2. Argonne National Laboratory, 9700 S. Cass Avenue, Building 208, Argonne, IL 60439 (United States)
Description
The recent interest in the Small Modular Reactors for their potential increased economic competitiveness has focused attention in part on reducing operational costs to offset those plant costs that do not benefit from the economies of scale of large traditional units. Plant economics is significantly driven by plant availability, which can be enhanced by means of innovative operating strategies that act to avert plant or unit trips. A strategy that involves fast runback of the power plant to avert a turbine trip following a disconnection from the grid has been developed and assessed for a typical sodium-cooled SMR (adopted for proof-of-principle demonstration). A classic control approach based on PID feedback controllers has been adopted for establishing a baseline for performance improvement. Simulations outcomes have shown that although the reactor power level can be appropriately reduced, the net result is a global cooling of the system circuits. Such system conditions do not facilitate the objective of a rapid reconnect to the grid once the issue has been resolved. Moreover, the classic approach requires relatively large control rod motion. An alternative MIMO (Multiple Input Multiple Output) control scheme on the other hand provides additional regulation flexibility by allowing for coordinated control actions on the mass flow rates and on the control rods. A Model-based Predictive Control implementation of the MIMO approach has ensured prompt power level reduction with reduced overcooling and control rod motion, facilitating a quicker reconnect to the grid. Such flexibility could lead to improved system availability. An investigation of the metal-fuel form as an alternate to the oxide fuel form and its wider experience base has been performed for the same operational transient. By comparing the plant response for these two different fuel forms, it has been possible to evaluate the favorable properties in terms of inherent safety and plant operation of the metal-fuelled core configuration. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-776-7
- Imprint Pagination
- 9 p.
Conference
- Title
- International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP 2014
- Dates
- 6-9 Apr 2014
- Place
- Charlotte, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54022525
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTROL ELEMENTS; NUCLEAR FUELS; OPERATING COST; OXIDES; PERFORMANCE; POWER PLANTS; REGULATIONS; SMALL MODULAR REACTORS; TRANSIENTS; TURBINES
- Descriptors DEC
- CHALCOGENIDES; COST; ENERGY SOURCES; EQUIPMENT; FUELS; LAWS; MACHINERY; MATERIALS; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; TURBOMACHINERY
Optional Information
- Notes
- 13 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)