Trace coupled with PARCS benchmark against Leibstadt plant data during the turbine trip test
Creators
- 1. KernkraftwerkLeibstadt AG, Leibstadt (Switzerland)
- 2. Universitat Politecnica de Valencia (ISIRYM/UPV), Valencia, (Spain). Institute for Industrial, Radiophysical and Environmental Safety
Description
In order to enhance the modeling of Nuclear Power Plant Leibstadt (KKL), the coupling of 3D neutron kinetics PARCS code with TRACE has been developed. To test its performance a complex transient of Turbine Trip has been simulated comparing the results with the existing plant data of Turbine Trip test. For this transient also Cross Sections have been generated and used by PARCS. The thermal-hydraulic TRACE model is retrieved from the already existing model. For the benchmarking the Turbine Trip transient has been simulated according to the test resulting in the closure of the turbine control valve (TCV) and the following opening of the bypass valve (TBV). This transient caused a pressure shock wave towards the Reactor Pressure Vessel (RPV) which provoked the decreasing of the void level and the consequent slight power excursion. The power control capacity of the system showed a good response with the procedure of a Selected Rod Insertion (SRI) and the recirculation loops performance which resulted in the proper thermal power reduction comparable to APRM data recorder from the plant. The comparison with plant data shows good agreement in general and assesses the performance of the coupled model. Due to this, it can be concluded that the coupling of PARCS and TRACE codes in addition with the Cross Section used works successfully for simulating the behavior of the reactor core during complex plant transients. Nevertheless the TRACE model shall be improved and the core neutronics corresponding to the test shall be used in the future to allow quantitative comparison between TRACE and plant recorded data. (author)
Files
45110528.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- INIS-BR--14607
Conference
- Title
- international nuclear atlantic conference
- Acronym
- INAC 2013
- Dates
- 24-29 Nov 2013
- Place
- Recife, PE (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 45110528
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COUPLING; CROSS SECTIONS; LEIBSTADT REACTOR; NUCLEAR POWER PLANTS; P CODES; PERFORMANCE; REACTOR CORES; THERMAL HYDRAULICS; TRANSIENTS; TURBINES; VALVES
- Descriptors DEC
- BWR TYPE REACTORS; COMPUTER CODES; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FLUID MECHANICS; HYDRAULICS; MACHINERY; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TURBOMACHINERY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs., 13 figs., 4 tabs.