General aspects of WWER technology. Russian computer codes for safety assessment

Training Modules 1. Layout of NPP with WWER-type reactor 2. WWER Safety Systems 3. Analytical Simulator WWER-1000 4. WWER fuel 4.1 Chemical composition, types and basic operational characteristics of nuclear fuel. Fuel behavior under irradiation. Modern technical requirements for nuclear fuel 4.2 WWER fuel. The use of burnable absorber 4.3 Nuclear fuel fabrication techniques. Perspective fuel types 4.4 Technological scheme of nuclear fuel fabrication: from the powder to fuel. Tech Tour to MSZ. 5. Personnel Management for NPP with WWER-type Reactor 6. Computer codes for safety assessment 6.1 Codes and computational tasks 6.2 Russian computer codes for safety assessment 6.3 Status of MCU code. A modular structure of MCU code. Input data, geometry, source and tally description. Sample problems and practice 7. Management issues of NPP with WWER 7.1 Reactor Island 7.2 Turbine Island 7.3 NPP under the operation. Technical Tour to NPP 8. Deterministic safety analysis in severe accident analysis. Computer code SOCRAT 8.1 Getting started with SOCRAT modeling: general description of SOCRAT and modeling of thermal hydraulics 8.2 Modeling of core degradation 8.3 Modeling of the late stage of a severe accident (in-vessel and ex-vessel stages) 8.4 Modeling of fission products build-up, release, transport and deposition 8.5 Examples of practical application of SOCRAT code in resolving the safety issues 9. Methods ensuring efficiency and correctness of estimations of radiation situation and radiation consequences for the environment and population. Russian computer codes designed for that purpose. 9.1 SI in the site selection process, public debates and hearings 9.2 RSES (State Unified System of Prevention and Response to Emergence Situations). Russian emergency response systems to radiation hazards. 9.3 Practical studies with demonstration of software packages for forecasting of radiation situation after NPP accident (input of the initial data, calculation, results’ analysis, use of meteorological data) 9.4 Examples of the use of software packages to predict radiation situation after the accident at Fukushima 10. Final test 216 h total (122 h of lectures + 94 h of hands-on sessions)