Workforce Development Programmes
Deterministic Safety Analysis of Nuclear Power Plants
Course Code : NS02 | Duration : 5 Days | Level : Advanced Nuclear Safety
Safety analysis forms a major part of the design and licensing process for nuclear power plants. Safety analysis is carried out to ensure that the various provisions for safety are adequate to maintain the plant parameters within acceptable limits under various postulated conditions including normal operation, anticipated operational occurrences and accidents.
This programme on 'Deterministic Safety Analysis of Nuclear Power Plants' introduces the
different approaches to safety analysis, postulated initiating events and their categorization.
The two approaches of deterministic safety analysis, viz., conservative deterministic safety
analysis and the Best Estimate Plus Uncertainty
( BEPU ) analysis are explained. Consideration of
the non-availability of systems and components (e.g. single failure criterion) and the effects of
nodalization and plant modelling (user effects) are dealt with. The computer codes for LOCA
analysis and their verification and validation are discussed. The application of Dsa to safety
analysis of NPPs and the regulatory review of DSA are also dealt with.
MODULES
- Introduction to safety analysis
- Deterministic and probabilistic safety analyses
- Different plant states of NPPs and
Postulated Initiating Events (PIEs)
- Grouping of PIEs – anticipated Operational Occurrences ( AOOs), Design Basis Accidents (DBAs), b eyond Design Basis Accidents ( BDBAs)/Severe Accidents (SAs)
- Acceptance criteria for different categories of PIEs
- Conservative Deterministic Safety analysis (DSA )
- Credit for operator action on conservative basis
- Best estimate Plus uncertainty ( BEPU ) analysis
- Why Best Estimate (BE ) approach
- Sensitivity analysis and uncertainty analysis
- Initial and boundary conditions
- Availability of systems
- Application of single failure criterion
- Loss of off-site power
- Nodalization and plant modelling
- User effects and user qualification
- Application of DSA to safety analysis of NPPs
- Application of DSA to a typical design basis accident
- Loss of Coolant Accident (LOCA)
- Introduction to computer codes for loca analysis
- Code verification and validation
- Experimental studies for code validation
- Typical loca analysis
- Introduction to analysis of Beyond Design Basis Accidents (BDBAs) and severe Accidents (SAs)
- Regulatory review of DSA
- Relation of DSA to
- Engineering aspects of safety
- Probabilistic safety analysis
ATTENDEES WILL LEARN ABOUT
- Safety analysis approach
- Identification of PIEs and their categorization
- Conservative and BEPU approaches for deterministic safety analysis of NPPs
- Consideration of non-availability of systems and the effects of nodalization and plant modelling
- Application of DSA to a typical DBA such as LOCA
- Basics of computer codes for LOCA analysis
- Verification and validation of computer codes
- Introduction to analysis of BDBAs
- Regulatory review of DSA
REQUISITE QUALIFICATION
This is an advanced programme on safety analysis of NPPs. To get optimum benefits from the programme, participants should have knowledge of nuclear reactors and power plants. Knowledge of the basics of two-phase flow and nuclear safety aspects will be useful. The minimum qualification of the participants for attending the programme is a bachelor's degree in science/ engineering. It is advisable to attend the programme on ' Introduction to Nuclear Safety' before attending this programme.
Who Should Attend ?
- Nuclear safety advisors and consultancy firms
- Engineering design consultants and technical service providers in the nuclear sector
- Organizations (manufacturing,EPC, utility companies) serving and/or planning to enter the nuclear sector
- Employees of NPPs
- Personnel of NPP design, construction and operating organizations
- Representatives from energy departments of the government
- Environmental protection agencies
- Personnel involved in the safety analysis of NPPs
- Regulatory bodies
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