Improvement of steam separator in boiling water reactors
Description
The potential to improve the function of the steam separator is identified and explored by scaled air-water tests and validated CFD calculations. It can be outlined that requirements on a modern steam separator for BWR plants will be fulfilled, combined with very good operational experience of the existing separator designs (e.g. material, layout). With the new steam separator design, modern high performance fuel assembly designs can be used for various core loading strategies (e.g. low leakage). This allows an increased thermal power of up to +50 % for the fuel element clusters in the center of the core with high radial peaking factors. In addition, any problems with unallowable high moisture at the turbine are solved with the new design, which have been identified for running BWR plants with the old steam separator design after applying new core loading patterns (e.g. after power uprates). A compatible steam separator design for all running BWRs is ready to launch. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2013. Dokumentation
Publishing Information
- Imprint Title
- Annual meeting on nuclear technology 2013. Documentation
- Imprint Pagination
- 1142 p.
- Journal Page Range
- 6 p.
Conference
- Title
- Annual meeting on nuclear technology 2013
- Original Conference Title
- Jahrestagung Kerntechnik 2013
- Dates
- 14-16 May 2013
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 45049727
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; DESIGN; FLUID MECHANICS; LEAKS; MOISTURE; PUMPS; REACTOR COMPONENTS; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; STEAM SEPARATORS; TEST FACILITIES; TURBINES; TWO-PHASE FLOW; VALIDATION
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; MACHINERY; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SEPARATION EQUIPMENT; SIMULATION; TESTING; THERMAL REACTORS; TURBOMACHINERY; VAPOR SEPARATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2013. Dokumentation