#nuclear engineering
Articles etiquetados con «nuclear engineering».
Etcheverry Hall: Engineering Infrastructure and Nuclear Research at UC Berkeley
Etcheverry Hall houses UC Berkeley's engineering departments and hosted the Berkeley Research Reactor from 1966 to 1987.
Energy Technology Engineering Center: Liquid Metal Testing at Santa Susana
ETEC was a research center in California that tested liquid metal components for nuclear reactors from 1966 to 1998.
Dry cask storage: Design, global deployment, and operational history
Overview of dry cask storage for spent nuclear fuel, including cask designs, global usage, and regulatory history.
Design-basis event in nuclear power
Definition and types of design-basis events in nuclear engineering, including earthquakes, fires, and beyond-design-basis accidents like Fuk...
Turbine hall: Design, components, and operational characteristics
Encyclopedic overview of the turbine hall in power plants, covering components, maintenance, and nuclear-specific challenges.
Startup neutron source
Neutron sources used to initiate nuclear chain reactions in reactors with fresh fuel or after prolonged shutdowns.
Edwin E. Kintner: Nuclear Pioneer and Three Mile Island Cleanup Leader
Edwin E. Kintner (1920–2010) was a US Navy captain and nuclear engineer who led the Three Mile Island cleanup and served on the Nautilus rea...
MOOSE (Multiphysics Object Oriented Simulation Environment)
MOOSE is an object-oriented C++ finite element framework for multiphysics solvers developed by Idaho National Laboratory.
Nuclear power plant refueling floor: Design, operations, and safety
Overview of the nuclear power plant refueling floor, its components, and refueling processes in PWRs and BWRs.
Masao Yoshida: Leadership during the Fukushima Daiichi Nuclear Disaster
Masao Yoshida was the plant manager of Fukushima Daiichi during the 2011 nuclear disaster, known for his decisive leadership and the 'Yoshid...
Active fuel length: Definition, components, and role in nuclear reactor design
Active fuel length is the length of fuel material in a nuclear fuel element, calculated as total rod length minus plenum and end plugs.
HDPE piping in nuclear power plant systems
Regulatory history and technical requirements for HDPE piping in US nuclear safety systems under ASME Code Section III.
Pressurized water reactor
Technical overview of the pressurized water reactor (PWR), the most common nuclear reactor type globally, covering design, history, and oper...
Residual heat removal system
The residual heat removal system (RHR) removes decay heat from nuclear reactors post-shutdown and serves as a key safety component in PWRs a...
Boiling water reactor
Technical overview of boiling water reactors (BWRs), the second most common nuclear reactor type, detailing design, safety, and evolution.
Pressurizer: Design, Operation, and Safety Functions in PWRs
Technical overview of the nuclear pressurizer: pressure control mechanisms, steam bubble dynamics, and safety relief systems in PWRs.
Babcock Borsig Service: Corporate Structure and Energy Industry Operations
Overview of Babcock Borsig Service GmbH, a German energy service provider and subsidiary of Bilfinger Berger.
Journal of Nuclear Fuel Cycle and Waste Technology
Academic journal published by the Korean Radioactive Waste Society covering nuclear engineering and waste technology.
Nuclear reactor coolant: types, functions, and safety dynamics
Overview of nuclear reactor coolants including water, molten metals, salts, and gases, their thermodynamic properties, and safety implicatio...
Nuclear reactor pressure vessel: Materials, radiation damage, and design
Technical overview of nuclear reactor pressure vessels, covering materials, radiation embrittlement, and manufacturing.