Nuclear Power Plant Reactor Training Manual: Boiling Water Reactor (BWR) Design at Japan TEPCO Fukushima Plant and U.S. Plants - Comprehensive Technical Data on Systems, Components, and Operations Ebook Tooltip Ebooks kunnen worden gelezen op uw computer en op daarvoor geschikte e-readers.

Learn the full details of the nuclear power reactor design at the heart of the 2011 Japanese TEPCO Fukushima Daiichi disaster with this training manual for nuclear workers published by the Nuclear Regulatory Commission (NRC). Every important safety system which has played a key role in the crisis is discussed in detail, including the reactor core, containment, emergency core cooling, and others. Procedures and contingencies, such as the loss of coolant accident (LOCA) suffered at Fukushima, are also detailed.

This General Electric reactor design is found in a number of American commercial nuclear facilities, including: Browns Ferry (Alabama), Brunswick (North Carolina), Cooper (Nebraska), Duane Arnold (Iowa), Fermi 2 (Michigan), Fitzpatrick (NY), Hatch (Georgia), Hope Creek (NJ), Peach Bottom (Pennsylvania), Vermont Yankee (Vermont).

General subject areas are classified by chapters. Systems which fall under the general classification are arranged as sections within the chapter. Where applicable each section follows the same format; i.e., introduction, system description, component description, system features and interrelations, and summary. The system introduction states the system purpose and functional classification. The purpose of the introduction is to orient the reader. The system description provides the reader with an overview of the system and its components. Attention is focused on major components and their purposes without including the detail found in the component description. The components are listed in basic flow path order or block diagram arrangement. Each component is described in appropriate detail with specific set points and capacities. The system features and interrelations section includes such items as the operational features and limitations. It also identifies interfaces with other systems.

Contents include: Plant Layout, Reactor Physics, Thermal Limits, Chemistry, Probabilistic Risk Assessment, Reactor Vessel Systems, Fuel and Controls Rods System, Control Rod, Recirculation, Main Steam, Condensate, Reactor Core Isolation, Process Instrumentation, Primary Containment, Secondary Containment, Neutron Monitoring, Display, Reactivity Control, Rod Worth Minimizer, Radioactive Waste Processing, Electrical, Emergency Core Cooling, Water and Air, Reactor Operations, and more.

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