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- Title
Thermohydraulic studies of sodium-cooled reactor facilities.
- Authors
Poplavksii, V.; Efanov, A.; Zhukov, A.; Kalyakin, S.; Sorokin, A.; Yuriev, Yu.
- Abstract
Thermohydraulic studies of reactor facilities with fast reactors are complex experimentally and computationally. Extensive experimental data are obtained on the velocity and temperature profiles, hydrodynamic resistance and heat emission, initial heat section, and interchannel mixing of the coolant in the fuel assemblies. These are used to develop engineering methods of performing thermohydraulic calculations of fuel assemblies as well as computational compute codes. The particulars of the hydrodynamics and heat transfer in intermediate heat exchangers and steam generators of reactor facilities with fast reactors are studied. This has made it possible to validate their thermohydraulic characteristics.
- Subjects
HYDRAULIC engineering; SODIUM cooled reactors; NUCLEAR facilities; FAST reactors; TEMPERATURE effect; HYDRODYNAMICS; NUCLEAR engineering; HEAT exchangers; STEAM generators
- Publication
Atomic Energy, 2010, Vol 108, Issue 4, p296
- ISSN
1063-4258
- Publication type
Article
- DOI
10.1007/s10512-010-9292-1