Metallic insulation transport and strainer clogging tests
Creators
- 1. Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland). Nuclear Safety Dept.
- 2. Imatran Voima Oy, Vantaa (Finland). Power Plant Lab.
Description
Experiments to probe the transport and clogging properties of metallic (metal reflective) insulation have been carried out in order to provide data for evaluation of their influence on the emergency core cooling and containment spray systems of the Finnish boiling water reactors in the event of a design basis accident. The specific metallic insulation tested was DARMET, provided by Darchem Engineering Ltd. The inner foils of Darmet are dimped. Available literature on the metallic insulation performance under design basis accident conditions has been reviewed. On the basis of the review a parametric approach has been chosen for the transport and clogging experiments. This approach involves testing a wide size range of various shapes of foil pieces. Five sets of experiments have been carried out. The first three sets investigate transport properties of the foil pieces, starting from sedimentation in stagnant waste pool and proceeding to transport in horizontal and vertically circulating flows. The clogging experiments have been addressed the differential pressures obtained due to accumulation of both pure and metallic and a mixture of metallic and fibrous (mineral wool) depris. (4 refs., 24 figs., 2 tabs.)
Availability note (English)
MF available from INIS under the Report Number.Files
27041684.pdf
Files
(1.8 MB)
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Additional details
Publishing Information
- ISBN
- 951-47-9550-4
- Imprint Pagination
- 40 p.
- Report number
- STUK-YTO-TR--73
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 27041684
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SPRAY SYSTEMS; ECCS; IMPURITIES; LOSS OF COOLANT; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RELIABILITY; THERMAL INSULATION; TRANSPORT
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; CONTAINMENT SYSTEMS; COOLING SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- DLV1-G380--383.