Fast Sodium Reactors
Studies of Physics and Engineering Problems for Safety Increase and Burning of Actinides Efficiency for Advanced Fast Reactors.
Tech Area / Field
- FIR-REA/Reactor Concept/Fission Reactors
8 Project completed
Senior Project Manager
Tocheny L V
FEI (IPPE), Russia, Kaluga reg., Obninsk
- Experimental Designing Bureau of Machine Building (OKBM), Russia, N. Novgorod reg., N. Novgorod\nAll-Russian Scientific Research Institute of Non-Organic Materials named after A. Bochvar, Russia, Moscow
- Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan, Tokyo
Project summaryFurther development of nuclear energetic (NE) depends on two problems at any rate:
— ensuring maximum attainable safety level of NE, absolute exclusion of accidents as Chernobyl one;
— burning of radioactive wastes of NE, in the first place high level long-lived actinides which are accumulated as result of NE activities.
In principle fast reactors with sodium coolant are able to solve these two the most important for world energetic development problems due to features of their physics and technology.
Proposed project "Studies of Physics and Engineering Problems of Increase Safety and Burning of Actinides Efficiency of Advanced Fast Reactors" meets above-fixed aims and also aims of ISTC which are contained in development viable professional alternatives and long-term support of scientists and engineers concerned to development of military weapons earlier.
The first aim of project consists in the investigations and elaboration of 1300 MWe fast power reactor concept with maximal safety. They include calculational studies on nitride (15N) fuelled cores and conceptual studies and elaboration of reactor vessel and its internal structures. Core investigations include optimization of its parameters from point of view of maximum advance of its inherent safety features to exclude core destruction during the most severe accident – loss of flow without scram (LOFWS).
The second aim of project consists of the investigations of different cores – with oxide, nitride and uranium free ones – for the most efficient burning of plutonium and minor actinides – americium, neptunium, curium.
For uranium-free core physics and engineering experiments are envisaged for making data base necessary to design such cores.
Physics experiments include making insert of large enough sizes to model fuel with inert material at the available critical assembly at the BFS-2. Main spectral indexes and reactivity coefficients will be measured at this insert and corresponding calculations will be performed. Engineering experiments include development of technology to make materials with inert components of MgO and AlN, to make test samples and investigate their main features (melting temperature, thermal conductivity, etc.). Performed investigations will permit to choose the most appropriate options of cores in accordance with pointed aims, to substantiate their main parameters and to design proposals including all necessary input data for development of technical designs.