Preliminary analysis of basic reactor physics of the Dual Fluid Reactor - 15270
Creators
- 1. Department of Nuclear Engineering, Technical University Munich, Boltzmannstrasse 15, 85748 Garching (Germany)
- 2. E.ON Kernkraft GmbH, Tresckowstrasse 5, 30457 Hannover (Germany)
Description
The Dual Fluid Reactor (DFR) is a novel fast nuclear reactor concept invented by the IFK based on the Generation IV Molten Salt Reactor and the Liquid Metal Cooled Reactor. The DFR uses a chloride based molten fuel salt in order to harden the neutron spectrum. The molten fuel salt is cooled with a separated liquid lead loop, which in principle allows for higher power densities and better breeding performance. The DFR does not combine heat removal and breeding into a single circuit but separates the two functions into two independent circuits. Since there are attractive features mentioned in this design, the main task of this paper is to verify the model of the whole reactor based on this concept. For this purpose several calculations are presented, including steady state calculations, sensitivity calculations with regard to the nuclide cross sections, the temperature and geometry coefficient of keff as well as the burnup calculation. The Monte Carlo calculation codes MCNP, SERPENT and SCALE are used for the analysis. As expected the study shows a significant negative reactivity feedback with temperature in the overall fission zone. For the coupled coolant and reflector design the temperature feedback is rather small for practical purposes such as reactor control during normal operation. In the view of these results the DFR in principle can be self-regulated totally by the temperature change of its own fuel salt and consequently can rely on fully passive safety systems for accident management
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- ICAPP 2015 Proceedings
- Imprint Pagination
- 3390 p.
- Journal Page Range
- p. 1891-1901
Conference
- Title
- Nuclear Innovations for a low-carbon future
- Acronym
- ICAPP 2015
- Dates
- 3-6 May 2015
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49004984
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; DESIGN; FAST REACTORS; FEASIBILITY STUDIES; LIQUID METAL COOLED REACTORS; MOLTEN SALT FUELED REACTORS; NEUTRON SPECTRA; SPECIFICATIONS; TEMPERATURE COEFFICIENT
- Descriptors DEC
- EPITHERMAL REACTORS; FLUID FUELED REACTORS; MOLTEN SALT REACTORS; REACTIVITY COEFFICIENTS; REACTORS; SIMULATION; SPECTRA
Optional Information
- Notes
- 19 refs.; This record replaces 48095379