Published May 2003
| Version v1
Report
Current status and plans for development of NPP with BREST reactors
Creators
- 1. State Scientific Center of Russian Federation (SSC RF), Research and Development Institute of Power Engineering (RDIPE), Moscow (Russian Federation)
Description
Current status and plans for the development of nuclear power plant with a pilot lead-cooled 300 MW(e) rated fast reactor (BREST-OD-300) are presented in this paper. The development project was commenced by the order of Ministry for Atomic Energy in 1998 and includes detailed design documentations for BREST-OD-300 and on-site fuel cycle facilities, and R and D activities for design verification. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-101503-8
- Imprint Title
- Power reactors and sub-critical blanket systems with lead and lead-bismuth as coolant and/or target material. Utilization and transmutation of actinides and long lived fission products
- Imprint Pagination
- 221 p.
- Journal Page Range
- p. 41-42
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1348
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34087437
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DESIGN; FEASIBILITY STUDIES; FUEL CYCLE; LEAD; LIQUID METALS; LMFBR TYPE REACTORS; MIXED NITRIDE FUELS; PLANNING; PROGRAM MANAGEMENT; URANIUM NITRIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; BREEDER REACTORS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUIDS; FUELS; LIQUID METAL COOLED REACTORS; LIQUIDS; MANAGEMENT; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; PNICTIDES; REACTOR MATERIALS; REACTORS; SOLID FUELS; URANIUM COMPOUNDS
- Proposed descriptors and Free-text terms
- BREST-300 reactor