Variational nodal expansion method. Extension to three-dimensional cartesian geometry, and benchmarking with mox fuel
Description
SCORPIO-VVER system was implemented at Unit 1 of NPP Dukovany in 1998. Input and output data were recorded and analyzed during more than 5 months of operation. The results are used for determination of the quality of measurements and the precision of calculations provided by the system. Comparison with the results of the other systems working at NPP is performed as well. This paper describes the determination of quantities which are important for on-line analyses and for the operator's interface. Calculations of the basic reactor and primary circuit parameters are presented including comparison of results with outputs of other systems. The method of the 3D power distribution determination in reactor core is discussed and examples of results are presented in comparison with the output of the VK3 system and independent calculations (author) (ml)
Additional details
Publishing Information
- Imprint Title
- High burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
- Imprint Pagination
- vp.
- Journal Page Range
- p. 10
- Report number
- HPR--351-V1
Conference
- Title
- Enlarged HPG meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
- Dates
- 24-29 May 1999
- Place
- Loen (Norway)
INIS
- Country of Publication
- Norway
- Country of Input or Organization
- Norway
- INIS RN
- 38108739
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature, Conference
- Descriptors DEI
- ACCURACY; BENCHMARKS; BWR TYPE REACTORS; CALCULATION METHODS; CARTESIAN COORDINATES; COMPUTER CALCULATIONS; FUEL PINS; GEOMETRY; MIXED OXIDE FUELS; NEUTRON TRANSPORT; NODAL EXPANSION METHOD; POWER DISTRIBUTION; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS; VARIATIONAL METHODS; WATER COOLED REACTORS
- Descriptors DEC
- CALCULATION METHODS; COORDINATES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUELS; POWER REACTORS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 8 figs., 4 tabs