Safety assessment calculation procedure for operating VVER unit in maneuvering regimes
-
Maxim Uvakin
,
Igor Makhin
Abstract
This paper presents a test safety assessment calculation technique for operating high power VVER units in daily maneuvering regimes. The test of maneuvering operation is an actual problem of VVER reactors exploitation. Corresponding tests are classified as nuclear hazardous procedures which are accompanied by power variations, regulators actions and continuous space power field fluctuations. As a result a lot of possible reactor plant conditions can occur. This fact is taken into account during the safety assessment of such tests. The proposed technique is based on a conservative approach. The paper contains a step-by-step structure of the method, the description of the calculation procedures and the applied models for each step. Initial conditions for selected RIA accidents are given and justified. Conclusions important for the practice are supported by method application results analysis for assigned task. All calculations are conducted using the KORSAR/GP programming code with 3D-neutrion kinetic model.
© 2020 by Walter de Gruyter Berlin/Boston
Artikel in diesem Heft
- 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
Artikel in diesem Heft
- 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
