Preliminary assessment of modeling issues related to dynamics and control of graphite-moderated MSRs
Creators
- 1. Politecnico di Milano, Department of Energy, Nuclear Engineering Division, Via La Masa, 34 - 20156 Milano (Italy)
Description
The Molten Salt Reactor (MSR) is characterized by a complex physical environment, as a consequence of the unusual role of the molten salt, which acts simultaneously as fuel and coolant. Such unique feature requires the development of dedicated simulation tools, able to take into account peculiar phenomena of Circulating Fuel Reactors (CFR) such as the delayed neutron precursor (Dnp) drift and the subsequent decay out of the core. In this paper, reference is made to the Molten Salt Reactor Experiment (MSRE). The MSRE was an 8 MWth graphite-moderated MSR built at the Oak Ridge National Laboratory during the sixties. It represents a convenient validation framework due to the availability of both design and experimental data. The analysis is carried out by means of a dynamic model. All the main components of the experimental plant are simulated. On the basis of the available MSRE experimental data, the proposed model results sufficiently accurate to predict the plant response in terms of the most relevant variables. A preliminary analysis of the control strategy has been also carried out considering a reactor/slave radiator/master control, confirming this strategy as a safe and effective one
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of ICAPP 2011
- Imprint Pagination
- 2851 p.
- Journal Page Range
- p. 832-841
- Report number
- INIS-FR--13-0283
Conference
- Title
- The Power of Innovation
- Acronym
- ICAPP 2011 - Performance and Flexibility
- Dates
- 2-5 May 2011
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 44092872
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; HEAT TRANSFER; MOLTEN SALT FUELED REACTORS; MSRE REACTOR; REACTIVITY INSERTIONS; REACTOR KINETICS; REACTOR KINETICS EQUATIONS; TRANSIENTS; VALIDATION
- Descriptors DEC
- ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; EXPERIMENTAL REACTORS; FLUID FUELED REACTORS; GRAPHITE MODERATED REACTORS; KINETICS; MOLTEN SALT COOLED REACTORS; MOLTEN SALT REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TESTING; THERMAL REACTORS
Optional Information
- Notes
- 17 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/