Justification of Arrangement, Parameters, and Irradiation Capabilities of the MBIR Reactor Core at the Initial Stage of Operation
Creators
- 1. JSC "SSC RF - IPPE" (Russian Federation)
- 2. JSC ''NIKIET'' (Russian Federation)
- 3. JSC " SSC RIAR" (Russian Federation)
- 4. JSC "Science and Innovation" (Russian Federation)
Description
Reactor MBIR will start operating in the absence of loop channels, which represent technologically complex equipment. At the initial stage of operation this will make it possible, on the one hand, to develop technological modes of reactor facility operation with small amount of experimental devices, and on the other hand, with this development, to gradually fill the cells intended for the loop channels additional irradiation assemblies. For example, central loop channel occupies 7 cells in the center of the core. It is unreasonable to use all the seven cells for irradiation assemblies, because of their strong influence on each other. To eliminate this impact, it is possible to fill the central loop channel cells with three irradiation assemblies and four fuel assemblies. To level the energy release, it is reasonable to install one more irradiation assembly in the core and compensate the critically loss by installing 4 additional fuel assemblies on the core periphery. Consequently, core at the initial stage of operation will consist of 85 fuel assemblies (93 assemblies in the design), 8 cells with CPS control rods and 21 irradiation assemblies. Thus, the number of the irradiation cells can be increased from 17 to 21 at the initial stage of operation by eliminating central loop channel. Reactor power at this stage must be reduce from 150 to 137 MWt. With this modification of the core, fuel with the design plutonium weight content is used, enabling transition to a design version of the core without changing the fuel assemblies design. For the same reason, the neutron flux and damaging dose in the irradiation assemblies at the initial stage of operation are almost the same as the design values. The rate of damaging dose accumulation in the irradiation assemblies located in the core is from 16 to 16.7 dpa per micro-campaign (100 eff. days). Inner volume of one irradiation assembly is 2.28 l. General rate of damaging dose accumulation in the MBIR reactor at the initial stage of operation is 1370 dpa*l/year. In the BOR-60 reactor this parameter equals 300 dpa*l/year. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108618-1
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 6 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51006288
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOR-60 REACTOR; CONTROL ELEMENTS; FAST REACTORS; FUEL ASSEMBLIES; NEUTRON FLUX; NUCLEAR FUELS; PLUTONIUM; REACTOR CHANNELS; REACTOR CORES; SODIUM COOLED REACTORS
- Descriptors DEC
- ACTINIDES; BREEDER REACTORS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; POWER REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 5 refs., 6 figs.
- Secondary number(s)
- IAEA-CN--245-438