Published October 2006
| Version v1
Report
Thermohydraulic research for the core of the BREST reactor
Creators
- 1. State Scientific Center, Institute of Physics and Power Engineering (SSC SRF-IPPE), Obninsk (Russian Federation)
- 2. Federal State Unitary Enterprise Research and Development Institute of Power Engineering (NIKIET), Moscow (Russian Federation)
Description
The results of experimental and computational thermohydraulic research for the experimental demonstration lead-cooled fast reactor BREST are considered. Method of experiments and design of the model subassembly are described. The generalized recommendations (formula, graphic dependence) to estimate the Nusselt numbers and temperature non-uniformities along a perimeter of fuel pins of this reactor for a number of cases representing the greatest practical interest for thermohydraulic substantiation of the reactor core are given. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-111806-6
- Imprint Title
- Theoretical and experimental studies of heavy liquid metal thermal hydraulics. Proceedings of a technical meeting
- Imprint Pagination
- 323 p.
- Journal Page Range
- p. 213-225
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1520
Conference
- Title
- Technical meeting on theoretical and experimental studies of heavy liquid metal thermal hydraulics
- Dates
- 28-31 Oct 2003
- Place
- Karlsruhe (Germany)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38011884
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; FAST REACTORS; FUEL PINS; LEAD; LIQUID METAL COOLED REACTORS; REACTOR CORES; RECOMMENDATIONS
- Descriptors DEC
- ELEMENTS; EPITHERMAL REACTORS; FUEL ELEMENTS; METALS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 8 refs, 8 figs