Chapter 5 Safety of Nuclear Power Generation
Japanese Version
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【5-1-1】The Differences between Thermal and
Nuclear Power Plants
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【5-1-2】How a Boiling Water Reactor (BWR) Works
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【5-1-3】Structural Features of
Advanced Boiling Water Reactors (ABWR)
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【5-1-4】Features of
Advanced Boiling Water Reactors (ABWR)
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【5-1-5】
How a Pressurized Water Reactor (PWR) Works
【5-1-6】Cross-sections of Reactor Pressure Vessels
【5-1-7】
Structure of Fuel Assemblies and Control Rods
【5-1-8】Natural Uranium & Enriched Uranium
【5-1-9】Differences between Nuclear Power
and Nuclear Bombs
【5-1-10】About Neutron Irradiation Embrittlement
【5-1-11】About Ductile-Brittle Transition Temperature
【5-1-12】Monitoring Test Piece Inside Reactor Vessel and Ductile-Brittle Transition Temperature
【5-2-1】Inherent Safety of Nuclear Reactors
(Self-Limiting)
【5-2-2】Example of
an Emergency Core Cooling System (BWR)
【5-2-3】Example of
an Emergency Core Cooling System (PWR)
【5-2-4】Purposes of Periodic Inspections
of Nuclear Power Plants
【5-2-5】Methods for
Evaluating the Soundness of Equipment
【5-2-6】Changes in
the Nuclear Safety Regulatory System
【5-2-7】Nuclear Safety Regulation System
【5-2-8】New Regulatory Requirements for
Nuclear Power Plants
【5-2-10】Our Knowledge about Earthquakes
【5-2-11】Differences in Vibrations between
a Nuclear Power Plant and a Normal Building
【5-2-12】Appointment of Operator Management
【5-2-14】Environmental Assessment System
up to Construction of Power Station
【5-3-1】Historical Trends in Reported
Incidents and Failures at NPPs in Japan
【5-3-2】Troubleshooting
【5-3-3】
Equipment Utilization Rate of Nuclear Power Plant
【5-4-1】
Structure of the Chernobyl Nuclear Power Plant
【5-4-2】Course of the Chernobyl Nuclear Accident
【5-4-3】Causes of the Accident
at Chernobyl Nuclear Power Plant
【5-5-1】Overview of
the Three Mile Island Nuclear Accident
【5-6-1】Overview of
Accident at Mihama Nuclear Power Plant, Unit 2
【5-6-2】
Overview of Accident in Secondary Piping
at Mihama Nuclear Power Plant, Unit 3
【5-6-3】
Overview of Pipe Rupture in the Accident
at Hamaoka Nuclear Power Plant, Unit 1
【5-6-4】
Overview of the Sodium Leak Accident
at the Prototype Fast Breeder Reactor
【5-6-5】Overview of Modifications to
the Monju Prototype Fast Breeder Reactor
【5-6-6】Overview of the Criticality Accident
at the JCO Uranium Processing Plant
【5-7-1】International Nuclear Event Scale (INES)
【5-7-2】
World Association of Nuclear Operators (WANO)
【5-8-1】Enhancement of
the Nuclear Emergency Preparedness System
【5-8-2】Clarification of
Nuclear Emergency Categories (3 Stages)
【5-8-3】Expansion of
Nuclear Emergency Response Action Zone
【5-8-4】Radiation Protection for Residents
【5-8-5】Operational Intervention Level (OIL)
and protective measure
【5-8-6】Reinforcement of Network between
Government and Nuclear Power Plant Operators
【5-8-7】System for Prediction of
Environmental Emergency Dose Information
(SPEEDI)
【5-8-8】Nuclear Damage Compensation System
Chapter 5 Safety of Nuclear Power Generation
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