Molten-salt reactors: new possibilities, problems and solutions
- 631 Downloads
The possibilities of competitive development of a liquid-salt reactor with a cavity-type core for developing thorium-uranium breeder reactor and for burning transuranium elements from the spent fuel of power reactors are described. Such a reactor is characterized by fuel-cycle flexibility, since it is capable of operating with a wide spectrum of fuel and raw-materials loads without being stopped or structurally altered. Compared with thermal liquid-salt reactors with a graphite moderator, these reactors have deeply negative temperature coefficients of reactivity (–7·10–5°C–1), and the fuel salt is completely processed in 3–4 years. Such a reactor facility can be incorporated into any strategy for the development of nuclear power.
KeywordsSpend Fuel Reactor Facility Transuranium Element Molten Salt Reactor Liquid Bismuth
Unable to display preview. Download preview PDF.
- 1.Program of Development of Molten-Salt Breeder Reactors, Rep. ORNL-5018 (1974).Google Scholar
- 2.V. M. Novikov, V. V. Ignatiev, V. I. Fedulov, and V. N. Cherednikov, Molten-Salt Reactors: Prospects and Problems, Energoatomizdat, Moscow (1990).Google Scholar
- 3.V. Ignatiev and O. Feynberg, “Molten salt reactor for TRU transmutation without and with Th–U support,” Trans. ANS, 104,722–723 (2011).Google Scholar
- 4.E. Merle-Lucotte, S. Delpech, C. Renoult, et al., “Optimizing the burning efficiency and the deployment capacities of the molten salt fast reactor,” in: Proc. Global’09, Paris, France, Sepetmeber 6–11, 2009, pp. 1865–1872.Google Scholar
- 5.D. Sood, P. Iyer, R. Prasad, et al., “Plutonium trifluoride as a fuel for molten salt reactors: solubility studies,” Nucl. Tech., 27, 411–416 (1975).Google Scholar
- 6.V. V. Ignatiev, V. G. Subbotin, A. V. Merzlyakov et al., “Experimental study of the physical properties of salt melts containing sodium, lithium and beryllium fluorides,” At. Énerg., 101, No. 5, 364–372 (2006).Google Scholar
- 8.V. V. Ignatiev, A. I. Surenkov, V. G. Subbotin, et al., “Investigation of the corrosion resistance of nickel-based alloys in fluoride melts,” At. Énerg., 101, No. 4, 278–285 (2006).Google Scholar
- 9.A. V. Zagnitko and V. V. Ignatiev, “Equilibrium distribution of lanthanum, neodymium and thorium between fluoride salt melts and liquid bismuth,” Zh. Fiz. Khim., 86, No. 4, 1–6 (2012).Google Scholar
- 10.V. Ignatiev, O. S. Feynberg, V. K. Afonichkin, et al., “Advanced reactor technology options for utilization and transmutation of actinides in molten salt reactors,” in: IAEA TECDOC-1626, IAEA, Vienna (2009), pp. 128–168.Google Scholar