Validation of new CMS5-VVER nuclear data library using critical experiments and X2 full-core benchmarkjh
-
Rodolfo M. Ferrer
and
Tamer Bahadir
Abstract
Studsvik’s in-core fuel management code package CMS5- VVER, which includes the CASMO5-VVER lattice physics code and SIMULATE5-VVER three-dimensional nodal code, is currently in use for VVER-1000/1200 reactor analysis. Recently, a new commercially available CASMO5 nuclear data library has been generated based on the ENDF/B-VIII.0 evaluation. The ENDF/B-VIII.0 evaluation represents the state-ofthe- art in nuclear data and features new incident-neutron cross section evaluations from the CIELO project for 1H, 16O, 56Fe, 235U, 238U and 239Pu. A summary of the main features and validation of the new ENDF/B-VIII.0-based data library, referred to as E8R0 library, is presented in this work. Comparisons of predicted criticality and fission rate distributions to measurements from various hexagonal-lattice critical experiments, such as the ZR-6 (TIC) and P-Facility, show excellent agreement between the E8R0-based calculations and measurements. In addition, validation results are presented for CMS5-VVER using the new E8R0 library and the X2 VVER-1000 benchmark problem. These results indicate that the E8R0 library provides comparable accuracy to E7R1 results for the various reactor physics parameters such as critical boron concentration, temperature reactivity coefficients, and control rod worth.
© 2020 by Walter de Gruyter Berlin/Boston
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
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
