Finite element solution of the time-dependent SP3 equations using an implicit integration scheme
-
Boglárka Babcsány
,
Tamás Bartók
Abstract
A coupled thermal-hydraulics and reactor physics code system is being developed at the Institute of Nuclear Techniques of the Budapest University of Technology and Economics based on a higher-order transport approximation, the simplified spherical harmonics theory. The advantage of this method is that with a small increase in computational demand, it provides additional accuracy compared to diffusion theory. Besides - due to the fact that the multi-group SP3 and diffusion equations have a mathematically similar form - it requires minimal effort to implement an SP3 solution algorithm to an existing diffusion code. This paper focuses on an algorithm developed by the authors which applies Galerkin weighted residual method for spatial and theta method for time discretization. Results of two-group kinetic SP3 calculations performed with the SPNDYN code are also presented for various one-dimensional perturbations taking into account the delayed neutron precursor balance equations as well. The flexible nature of the SP3 equations makes the developed code a good starting point for more realistic dynamic calculations in the future.
© 2020 by Walter de Gruyter Berlin/Boston
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- Analysis of the startup physics tests of a VVER-1200 reactor with the KARATE- 1200 code system
- Numerical and experimental studies of the natural circulation mode during commissioning of Unit-1 Novovoronezh NPP-2
- SKETCH-N/ATHLET steady-state and dynamic coupling scheme verification on Kalinin-3 benchmark results
- Safety assessment calculation procedure for operating VVER unit in maneuvering regimes
- Assessment of the VVER-1200 reactivity coefficients on the basis of the data measured at the energy power levels
- Finite element solution of the time-dependent SP3 equations using an implicit integration scheme
- Radiation heating of VVER-4440 thermocouple
- Definition of requirements for REMIXand MOX-fuel effective employment for VVER-reactors
- Fuel cycle of light water reactor with full consumption of recycled uranium
- Imprint
Articles in the same Issue
- CONTENTS
- 10.3139/124.200030
- 10.3139/124.200031
- EDITORIAL
- 10.3139/124.200032
- Validation results of the BIPR-8A code, the new module of the software package KASKAD
- Validation of new CMS5-VVER nuclear data library using critical experiments and X2 full-core benchmarkjh
- Optimization of power microfield distribution in JA profiles RK3+ fuel assemblies with 4.68% average enrichment for VVER-440 prospective fuel cycles
- Cycle extension in Slovak VVER-440 reactors to 14 months
- "Full-Core" VVER-1000 calculation benchmark
- Solution of the VVER-1000 full core calculation benchmark by the KARATE code system
- Analysis of the startup physics tests of a VVER-1200 reactor with the KARATE- 1200 code system
- Numerical and experimental studies of the natural circulation mode during commissioning of Unit-1 Novovoronezh NPP-2
- SKETCH-N/ATHLET steady-state and dynamic coupling scheme verification on Kalinin-3 benchmark results
- Safety assessment calculation procedure for operating VVER unit in maneuvering regimes
- Assessment of the VVER-1200 reactivity coefficients on the basis of the data measured at the energy power levels
- Finite element solution of the time-dependent SP3 equations using an implicit integration scheme
- Radiation heating of VVER-4440 thermocouple
- Definition of requirements for REMIXand MOX-fuel effective employment for VVER-reactors
- Fuel cycle of light water reactor with full consumption of recycled uranium
- Imprint
