MR-6 type fuel elements cooling in natural convection conditions after the reactor shut down
Creators
- 1. Institute of Atomic Energy, Otwock Swierk (Poland)
Description
Natural cooling conditions of the nuclear fuel in the channel type reactor after its shut down are commonly determined with relatively high uncertainty. This is not only to he lack of adequate measurements of thermal parameters i.e. the residual power generation, the coolant flow and temperatures, but also due to indeterminate model of convection mechanism. The numerical simulation of natural convection in multitube fuel assembly in the fuel channel leads to various convection modes including evidently chaotic behaviour. To determine the real cooling conditions in the MARIA research reactor a series of experiments has been performed with fuel assembly equipped with a set of thermocouples. After some forced cooling period (the shortest was half an hour after the reactor shut down) the reactor was left with the only natural convection. Two completely different cooling modes have been observed. The MARIA core consists of series of individual fuel channel and so called bypasses, maintaining the hydraulic properties of the fuel channel, connected in parallel. Initially, the convection cells were established trough few so-called bypasses providing a very effective mode of cooling. In this mode the flow charts were identical to those existing in forced cooling mode. After certain period the system switched on the second cooling mode with natural circulation within the individual fuel cells. Higher temperatures and temperature fluctuations were characteristic for this mode approaching 30 deg in amplitude. In almost all the cases the system was switching few times between modes, but eventually remained in the second mode. The switching times were not regular and the process has a chaotic behaviour. (author)
Files
34030717.pdf
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Additional details
Publishing Information
- Publisher
- European Nuclear Society
- Imprint Place
- Berne (Switzerland)
- Imprint Title
- ENS RRFM 2002, Transactions. Oral Presentations and Posters
- Imprint Pagination
- p. 165-169
- Report number
- INIS-CH--0302
Conference
- Title
- 6th International Topical Meeting on Research Reactor Fuel Management, organized by the ENS in cooperation with the Belgian Nuclear Energy Society and the IAEA
- Acronym
- RRFM 2002
- Dates
- 17-20 Mar 2002
- Place
- Ghent (Belgium)
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 34030717
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ENRICHED URANIUM; FUEL ASSEMBLIES; FUEL CHANNELS; MARIA REACTOR; NATURAL CONVECTION; RESIDUAL POWER
- Descriptors DEC
- ACTINIDES; BERYLLIUM MODERATED REACTORS; CONVECTION; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MASS TRANSFER; MATERIALS; METAL MODERATED REACTORS; METALS; NUCLEAR POWER; POOL TYPE REACTORS; POWER; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs., 3 refs.