UNIVERSITI TENAGA NASIONAL MEHB513 Introduction to Nuclear Technology SEM 2 2014/2015 Group Assignment Fukushima Daiichi Nuclear Accident GROUP MEMBERS:

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UNIVERSITI TENAGA NASIONAL MEHB513 Introduction to Nuclear Technology SEM /2015 Group Assignment Fukushima Daiichi Nuclear Accident GROUP MEMBERS: 1) Muhammed Ariff bin Sarif ME ) Muhammad Izzatt bin Zulkepli ME ) Ng Joanne ME ) Nurin Irdina binti Mohd Anuar ME ) Muhammad Amni Fitri bin Azami ME088766

BEFORE THE ACCIDENT

Accident cause 11/03/2011, 2:46 p.m. local time (7 hours earlier Romanian time) near the Japanese island of Honshu was an earthquake of 9 on the Richter scale. The quake had an impact on section of north-east coast of Japan where they are located a series of nuclear power plants (NPP). Nuclear reactors have been shut down properly.

SITUATION AT THE TIME OF THE QUAKE At the time of the quake, reactor 4 had been de-fueled while 5 and 6 were in cold shutdown for planned regular maintenance (refueling). Reactors 1,2 and 3 were operating. At the moment of the quake, reactors were shut down automatically. Emergency generators started to run to pump the water needed to cool the reactors.

TSUNAMI The plant was protected by a seawall protection designed to withstand a 5.7 m tsunami. However, the 8-14-metre tsunami wave arrived 15 minutes after the earthquake. The entire plant was flooded, including low- lying generators and electrical devices in reactor basements. Connection to the electrical grid was broken.

Accident Characteristics Major external hazards affected site Station blackout Loss of some DC power Loss of ‘ultimate heat sink’ Failure to cool reactor cores Core melt and hydrogen generation Explosions Fission product releases over extended period

Evaluation for the impacts of the Fukushima nuclear accident on the technology development of new nuclear power plants and should include site, plant and reactor design, safety of plant and mitigation of nuclear accident.

Site Selection Geologic- related hazard Capable tectonic structures Surface faulting and deformation Potential ground motion Foundation conditions

Plan Improvements Elevated gravity drain tanks Pre-pressurized core flooding tanks Elevated tank natural circulation loops Passively cooled steam generator natural circulation Sump natural circulation

Plant Improvements Containment design Containment venting systems Instrumentation hardened against high radiation levels

NUCLEAR REACTOR DESIGN Nuclear power introduce to produce energy mix Understanding of existing designs but also in-depth knowledge of country-specific needs, conditions and other considerations. Project must be clearly understood and specified from the outset and balanced, comprehensive and up to date information about reactor designs, concepts and fuel cycle options must be made available and evaluated.

CONSIDERATION ON NUCLEAR DESIGN Size and stability of the national electricity grid, the seismicity of the selected site, the availability of water resources and the accessibility to waterways or other appropriate transportation routes. Level of technological maturity or innovation in the new NPP design. The level of completion of a design and its licensability in the new hosting country are also important considerations. Nuclear reactor design that is finalized and frozen, particularly one that has undergone licensing review in other countries, can minimize project uncertainties.

Modifications may be needed due to local regulatory requirements or due to the special characteristics of a site, a complete design. Striking a balance between the use of a large, inexpensive local labour force applying traditional construction techniques on site and the use of advanced construction techniques. Performance-specific considerations of a given design. Interest to examine the technology options that are being selected in other countries in the same region. Similar efficiencies could be achieved by selecting a widely used reactor design and by participating in the ‘owners’ group’ for that design. Fuel procurement and spent fuel and waste management.

CLASSIFICATIONS OF NUCLEAR REACTOR DESIGNS Advanced NPP designs are defined as those designs of current interest for which improvements over their predecessors and/or existing designs are expected. Advanced reactor designs can be divided into ‘evolutionary’ and ‘innovative’. Evolutionary design is an advanced design that achieves improvements over existing designs through small to moderate modifications. Innovative design is an advanced design which incorporates radical conceptual changes in design approaches or system configuration in comparison with existing practice.

Alternative classification was developed by the Generation IV International Forum, which divided nuclear reactor designs into four generations. The first generation consisted of the early prototype reactors of the 1950s and 60s. The second generation is largely made up of the commercial NPPs built since the 1970s which are still operating today. The Generation III reactors were developed in the 1990s and include a number of evolutionary designs that offer improved safety and economics. Generation IV, consists of innovative concepts where substantial R&D is still needed. Nuclear reactors classified depending on their neutron spectrum, or depending on the coolant they use to extract the fission energy from the core.

Reactors can be classified as water cooled reactors (WCRs), gas cooled reactors (GCRs), liquid metal cooled reactors (LMRs) and molten salt cooled reactors (MSRs). WCR category can be subdivided into boiling water reactors (BWRs), where the core is at relatively low pressure and the coolant is allowed to boil and pressurized water reactors (PWRs), where the core is at high pressure and the coolant remains a liquid. The WCR category can also be subdivided into light water reactors (LWRs) and heavy water reactors (HWRs) that use deuterium water. Finally, depending on the size of the plant, nuclear reactors can be classified as ‘small’ (with an output of less than 300 MW(e)), ‘medium’ (between 300 and 700 MW(e)) and ‘large’ (more than 700 MW(e)).

Base Plant Elevation Seawall Height Waterproofing of Backup Power Systems Emergency Power System Elevation Construction and Commission Dates