Background
Consideration of severe accidents in a Nuclear Power Plant (NPP) design is an essential component of Defence in Depth (DID) approach used in nuclear safety. Severe accidents have a very low probability, but can have significant consequences resulting from nuclear fuel degradation/damage. Computer codes (deterministic and Probabilistic) are essential tools for understanding how the reactor and its containment might respond under severe accident conditions and their probability of failure. The codes are used as a tool to support engineering judgement, based on which specific measures to mitigate the consequences of severe accidents are taken in NPP design and are also used to determine accident management strategies. Simulators are used for training of operators, students and faculty.
The aims of severe accident analysis are:
• To evaluate the ability of
the design to withstand severe accidents; Objective The objective of this conference
is to bring the experts in this field at one platform and share the experience
and knowledge on different aspects of the severe accidents and management. This
would help to create a virtual centre for continuous analysis of severe
accidents of all the types of civil nuclear power plants in the Indian scene
addressing the following thrust areas:
• To identify particular
vulnerabilities;
• To assess the equipment and instrmentation that could
manage and monitor the course of the accident;
• To mitigate accident
effects;
• To develop a severe accident management programme;
• To provide
input for off-site emergency planning;
Three severe accidents have taken
place in the 60-years of the history of civil nuclear power generation. These
are:
Three Mile Island (USA 1979) where the reactor was severely damaged but
radiation was contained and there were no adverse health or environmental
consequences.
Chernobyl (Ukraine 1986) where the destruction of the reactor
by reactivity transient, steam explosion and fire killed 31 people and had
significant health and environmental consequences.
Fukushima (Japan 2011)
where three old reactors (together with a fourth) were destroyed due to loss of
cooling resulting from incapacitating of the emergency power supply due to
tsunami
1. Modeling & Simulation for
thermal hydraulics of Nuclear Reactors
2. Code Development &
Validation
3. Comparison between Fukushima, Chernobyl & TMI
accidents
4. Hydrogen Phenomenon and management
5. Emergency and Severe
Accident Analysis: responses & procedures
6. Spent fuel pool/pond
management
7. Operational Safety Improvements
8. Modeling of transport of
FP (Fission Product) in Environment
9. Thermal Hydraulics in Safety
Assessment
10. Natural Circulation & Passive Systems
11. Air
Ingression
12. Steam explosion