Published 2002
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Hydraulic characteristics of the Maria reactor fuel channel
Description
The Maria reactor has two primary cooling - the primary cooling for the reactor pool and the primary circuit for the fuel channels. Due to high thermal fluxes as a large power generated in the fuel element it is necessary to maintain elevated pressure in the fuel channels primary circuit. In the work the fuel channel hydraulic characteristics without tubing's linking it with the headers and without of the fuel channel with tubing have been performed. Based on the experimental results the pressure drop versus the flow rate and the impact of water temperature on pressure drop is presented. (author)
Availability note (English)
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35019650.pdf
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Additional details
Additional titles
- Original title (Polish)
- Charakterystyka hydrauliczna kanalu paliwowego reaktora Maria
Publishing Information
- Imprint Pagination
- 26 p.
- ISSN
- 1232-5317
- Report number
- IAE--88/A
INIS
- Country of Publication
- Poland
- Country of Input or Organization
- Poland
- INIS RN
- 35019650
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ERRORS; FLOW RATE; FUEL CHANNELS; FUEL ELEMENTS; HEAT FLUX; HYDRAULICS; MARIA REACTOR; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0273-0400 K; WWER TYPE REACTORS
- Descriptors DEC
- BERYLLIUM MODERATED REACTORS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICS; METAL MODERATED REACTORS; POOL TYPE REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 16 figs, 5 tabs