Searching for reactor : 91 results found | RSS Feed for this search

1 2 3 4

22.921 Nuclear Power Plant Dynamics and Control (MIT) 22.921 Nuclear Power Plant Dynamics and Control (MIT)

Description

This short course provides an introduction to reactor dynamics including subcritical multiplication, critical operation in absence of thermal feedback effects and effects of Xenon, fuel and moderator temperature, etc. Topics include the derivation of point kinetics and dynamic period equations; techniques for reactor control including signal validation, supervisory algorithms, model-based trajectory tracking, and rule-based control; and an overview of light-water reactor startup. Lectures and demonstrations employ computer simulation and the use of the MIT Research Reactor. This course is offered during the Independent Activities Period (IAP), which is a special 4-week term at MIT that runs from the first week of January until the end of the month. This short course provides an introduction to reactor dynamics including subcritical multiplication, critical operation in absence of thermal feedback effects and effects of Xenon, fuel and moderator temperature, etc. Topics include the derivation of point kinetics and dynamic period equations; techniques for reactor control including signal validation, supervisory algorithms, model-based trajectory tracking, and rule-based control; and an overview of light-water reactor startup. Lectures and demonstrations employ computer simulation and the use of the MIT Research Reactor. This course is offered during the Independent Activities Period (IAP), which is a special 4-week term at MIT that runs from the first week of January until the end of the month.

Subjects

reactor | reactor | nuclear reactor | nuclear reactor | radiation | radiation | feedback | feedback | light-water reactor | light-water reactor | neutron | neutron | reactor operation | reactor operation | reactor startup | reactor startup | reactor shutdown | reactor shutdown | reactor emergency | reactor emergency | pressurized water reactor | pressurized water reactor | PWR | PWR | BWR | BWR | criticality | criticality | reactor design | reactor design

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses-energy.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.251 Systems Analysis of the Nuclear Fuel Cycle (MIT) 22.251 Systems Analysis of the Nuclear Fuel Cycle (MIT)

Description

This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Also covered are the principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers. This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Also covered are the principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers.

Subjects

nuclear fuel | nuclear fuel | nuclear fuel cycle | nuclear fuel cycle | thorium fuel | thorium fuel | dry recycling | dry recycling | transmutation | transmutation | radioactive waste disposal | radioactive waste disposal | waste storage | waste storage | nuclear waste | nuclear waste | nuclear reactor analysis | nuclear reactor analysis | fuel cell design | fuel cell design | reactor design | reactor design | fast reactors | fast reactors | breeder reactors | breeder reactors | CANDU reactor | CANDU reactor | light water reactor | light water reactor | LWR | LWR | nuclear non-proliferation | nuclear non-proliferation | plutonium recycling | plutonium recycling

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.921 Nuclear Power Plant Dynamics and Control (MIT)

Description

This short course provides an introduction to reactor dynamics including subcritical multiplication, critical operation in absence of thermal feedback effects and effects of Xenon, fuel and moderator temperature, etc. Topics include the derivation of point kinetics and dynamic period equations; techniques for reactor control including signal validation, supervisory algorithms, model-based trajectory tracking, and rule-based control; and an overview of light-water reactor startup. Lectures and demonstrations employ computer simulation and the use of the MIT Research Reactor. This course is offered during the Independent Activities Period (IAP), which is a special 4-week term at MIT that runs from the first week of January until the end of the month.

Subjects

reactor | nuclear reactor | radiation | feedback | light-water reactor | neutron | reactor operation | reactor startup | reactor shutdown | reactor emergency | pressurized water reactor | PWR | BWR | criticality | reactor design

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see https://ocw.mit.edu/terms/index.htm

Site sourced from

https://ocw.mit.edu/rss/all/mit-allsimplifiedchinesecourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.921 Nuclear Power Plant Dynamics and Control (MIT)

Description

This short course provides an introduction to reactor dynamics including subcritical multiplication, critical operation in absence of thermal feedback effects and effects of Xenon, fuel and moderator temperature, etc. Topics include the derivation of point kinetics and dynamic period equations; techniques for reactor control including signal validation, supervisory algorithms, model-based trajectory tracking, and rule-based control; and an overview of light-water reactor startup. Lectures and demonstrations employ computer simulation and the use of the MIT Research Reactor. This course is offered during the Independent Activities Period (IAP), which is a special 4-week term at MIT that runs from the first week of January until the end of the month.

Subjects

reactor | nuclear reactor | radiation | feedback | light-water reactor | neutron | reactor operation | reactor startup | reactor shutdown | reactor emergency | pressurized water reactor | PWR | BWR | criticality | reactor design

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see https://ocw.mit.edu/terms/index.htm

Site sourced from

https://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.39 Integration of Reactor Design, Operations, and Safety (MIT) 22.39 Integration of Reactor Design, Operations, and Safety (MIT)

Description

This course integrates studies of engineering sciences, reactor physics and safety assessment into nuclear power plant design. Topics include materials issues in plant design and operations, aspects of thermal design, fuel depletion and fission-product poisoning, and temperature effects on reactivity, safety considerations in regulations and operations, such as the evolution of the regulatory process, the concept of defense in depth, General Design Criteria, accident analysis, probabilistic risk assessment, and risk-informed regulations. This course integrates studies of engineering sciences, reactor physics and safety assessment into nuclear power plant design. Topics include materials issues in plant design and operations, aspects of thermal design, fuel depletion and fission-product poisoning, and temperature effects on reactivity, safety considerations in regulations and operations, such as the evolution of the regulatory process, the concept of defense in depth, General Design Criteria, accident analysis, probabilistic risk assessment, and risk-informed regulations.

Subjects

nuclear reactor | nuclear reactor | nuclear power | nuclear power | NRC | NRC | PWR | PWR | pressurized water reactor | pressurized water reactor | GFR | GFR | LWR | LWR | light water reactor | light water reactor | nuclear safety | nuclear safety | meltdown | meltdown | nuclear risk | nuclear risk | PRA | PRA | probabalistic risk assessment | probabalistic risk assessment | risk assessment | risk assessment | thermal | thermal | hydraulic | hydraulic | nuclear fuel | nuclear fuel | nuclear waste | nuclear waste | accident | accident | radiation radioactivity | radiation radioactivity | nuclear plant | nuclear plant | cooling Seabrook | cooling Seabrook | fission | fission | uranium | uranium | half-life | half-life | plutonium | plutonium | economics of nuclear power | economics of nuclear power | materials slection | materials slection | IRIS | IRIS | materials selection | materials selection

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses-energy.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.251 Systems Analysis of the Nuclear Fuel Cycle (MIT)

Description

This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Also covered are the principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers.

Subjects

nuclear fuel | nuclear fuel cycle | thorium fuel | dry recycling | transmutation | radioactive waste disposal | waste storage | nuclear waste | nuclear reactor analysis | fuel cell design | reactor design | fast reactors | breeder reactors | CANDU reactor | light water reactor | LWR | nuclear non-proliferation | plutonium recycling

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see https://ocw.mit.edu/terms/index.htm

Site sourced from

https://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.05 Neutron Science and Reactor Physics (MIT) 22.05 Neutron Science and Reactor Physics (MIT)

Description

This course introduces fundamental properties of the neutron. It covers reactions induced by neutrons, nuclear fission, slowing down of neutrons in infinite media, diffusion theory, the few-group approximation, point kinetics, and fission-product poisoning. We emphasize the nuclear physics basis of reactor design and its relationship to reactor engineering problems. This course introduces fundamental properties of the neutron. It covers reactions induced by neutrons, nuclear fission, slowing down of neutrons in infinite media, diffusion theory, the few-group approximation, point kinetics, and fission-product poisoning. We emphasize the nuclear physics basis of reactor design and its relationship to reactor engineering problems.

Subjects

reactor physics | reactor physics | reactor layout | reactor layout | binding energy | binding energy | fission | fission | neutron cross-sections | neutron cross-sections | liquid drop model | liquid drop model | neutron life cycle | neutron life cycle | criticality | criticality | accidents | accidents | neutron flux | neutron flux | neutron current | neutron current | neutron diffusion theory | neutron diffusion theory | elastic neutron scattering | elastic neutron scattering | group diffusion method | group diffusion method | subcritical multiplication | subcritical multiplication | point kinetics | point kinetics | dynamic period equation | dynamic period equation | inhour equation | inhour equation | shutdown margin | shutdown margin

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.39 Integration of Reactor Design, Operations, and Safety (MIT) 22.39 Integration of Reactor Design, Operations, and Safety (MIT)

Description

This course integrates studies of engineering sciences, reactor physics and safety assessment into nuclear power plant design. Topics include materials issues in plant design and operations, aspects of thermal design, fuel depletion and fission-product poisoning, and temperature effects on reactivity, safety considerations in regulations and operations, such as the evolution of the regulatory process, the concept of defense in depth, General Design Criteria, accident analysis, probabilistic risk assessment, and risk-informed regulations.Technical RequirementsSpecial software is required to use some of the files in this course: .exe and .zip. The .in files are input data files. This course integrates studies of engineering sciences, reactor physics and safety assessment into nuclear power plant design. Topics include materials issues in plant design and operations, aspects of thermal design, fuel depletion and fission-product poisoning, and temperature effects on reactivity, safety considerations in regulations and operations, such as the evolution of the regulatory process, the concept of defense in depth, General Design Criteria, accident analysis, probabilistic risk assessment, and risk-informed regulations.Technical RequirementsSpecial software is required to use some of the files in this course: .exe and .zip. The .in files are input data files.

Subjects

nuclear reactor | nuclear reactor | nuclear power | nuclear power | NRC | NRC | PWR | PWR | pressurized water reactor | pressurized water reactor | GFR | GFR | nuclear safety | nuclear safety | meltdown | meltdown | nuclear risk | nuclear risk | PRA | PRA | probabalistic risk assessment | probabalistic risk assessment | risk assessment | risk assessment | thermal | thermal | hydraulic | hydraulic | nuclear fuel | nuclear fuel | nuclear waste | nuclear waste | accident | accident | radiation | radiation | radioactivity | radioactivity | nuclear plant | nuclear plant | cooling | cooling | seabrook | seabrook | fission | fission | uranium | uranium | half-life | half-life | plutonium | plutonium

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.312 Engineering of Nuclear Reactors (MIT) 22.312 Engineering of Nuclear Reactors (MIT)

Description

This course covers engineering principles of nuclear reactors, emphasizing power reactors. Topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. Engineering considerations in reactor design are also covered. The course objective is to understand and model the thermal-hydraulic and mechanical phenomena key to the effective, reliable and safe design and operation of nuclear systems.This course is taught by Prof. Jacopo Buongiorno. More information is available on his Web site. This course covers engineering principles of nuclear reactors, emphasizing power reactors. Topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. Engineering considerations in reactor design are also covered. The course objective is to understand and model the thermal-hydraulic and mechanical phenomena key to the effective, reliable and safe design and operation of nuclear systems.This course is taught by Prof. Jacopo Buongiorno. More information is available on his Web site.

Subjects

power | power | reactors | reactors | thermodynamics | thermodynamics | heat generation and removal | heat generation and removal | coolant flow | coolant flow | single-phase coolant flow | single-phase coolant flow | two-phase coolant flow | two-phase coolant flow | reactor design | reactor design | structural mechanics | structural mechanics

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.313 Thermal Hydraulics in Nuclear Power Technology (MIT) 22.313 Thermal Hydraulics in Nuclear Power Technology (MIT)

Description

This course covers the thermo-fluid dynamic phenomena and analysis methods for conventional and nuclear power stations. Specific topics include: kinematics and dynamics of two-phase flows; steam separation; boiling, instabilities, and critical conditions; single-channel transient analysis; multiple channels connected at plena; loop analysis including single and two-phase natural circulation; and subchannel analysis.Starting in Spring 2007, this course will be offered jointly in the Departments of Nuclear Science and Engineering, Mechanical Engineering, and Chemical Engineering, and will be titled "Thermal Hydraulics in Power Technology." This course covers the thermo-fluid dynamic phenomena and analysis methods for conventional and nuclear power stations. Specific topics include: kinematics and dynamics of two-phase flows; steam separation; boiling, instabilities, and critical conditions; single-channel transient analysis; multiple channels connected at plena; loop analysis including single and two-phase natural circulation; and subchannel analysis.Starting in Spring 2007, this course will be offered jointly in the Departments of Nuclear Science and Engineering, Mechanical Engineering, and Chemical Engineering, and will be titled "Thermal Hydraulics in Power Technology."

Subjects

reactor | reactor | nuclear reactor | nuclear reactor | thermal behavior | thermal behavior | hydraulic | hydraulic | hydraulic behavior | hydraulic behavior | heat | heat | modeling | modeling | steam | steam | stability | stability | instability | instability | thermo-fluid dynamic phenomena | thermo-fluid dynamic phenomena | single-heated channel-transient analysis | single-heated channel-transient analysis | Multiple-heated channels | Multiple-heated channels | Loop analysis | Loop analysis | single and two-phase natural circulation | single and two-phase natural circulation | Kinematics | Kinematics | two-phase flows | two-phase flows | subchannel analysis | subchannel analysis | Core thermal analysis | Core thermal analysis

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.06 Engineering of Nuclear Systems (MIT) 22.06 Engineering of Nuclear Systems (MIT)

Description

In this course, students explore the engineering design of nuclear power plants using the basic principles of reactor physics, thermodynamics, fluid flow and heat transfer. Topics include reactor designs, thermal analysis of nuclear fuel, reactor coolant flow and heat transfer, power conversion cycles, nuclear safety, and reactor dynamic behavior. In this course, students explore the engineering design of nuclear power plants using the basic principles of reactor physics, thermodynamics, fluid flow and heat transfer. Topics include reactor designs, thermal analysis of nuclear fuel, reactor coolant flow and heat transfer, power conversion cycles, nuclear safety, and reactor dynamic behavior.

Subjects

nuclear power overview | nuclear power overview | accelerators | accelerators | reactor physics review | reactor physics review | thermal parameters | thermal parameters | PWR | PWR | BWR | BWR | reactor design | reactor design | thermal analysis of fuel | thermal analysis of fuel | ideal gas and incompressible fluid models | ideal gas and incompressible fluid models | single phase coolant heat transfer | single phase coolant heat transfer | pure substance model | pure substance model | two-phase coolant flow and heat transfer | two-phase coolant flow and heat transfer | power cycles | power cycles | nuclear safety | nuclear safety

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.05 Neutron Science and Reactor Physics (MIT) 22.05 Neutron Science and Reactor Physics (MIT)

Description

This course introduces fundamental properties of the neutron. It covers reactions induced by neutrons, nuclear fission, slowing down of neutrons in infinite media, diffusion theory, the few-group approximation, point kinetics, and fission-product poisoning. It emphasizes the nuclear physics bases of reactor design and its relationship to reactor engineering problems. This course introduces fundamental properties of the neutron. It covers reactions induced by neutrons, nuclear fission, slowing down of neutrons in infinite media, diffusion theory, the few-group approximation, point kinetics, and fission-product poisoning. It emphasizes the nuclear physics bases of reactor design and its relationship to reactor engineering problems.

Subjects

reactor physics | reactor physics | neutron | neutron | reactor layout | reactor layout | binding energy | binding energy | fission | fission | neutron cross-sections | neutron cross-sections | liquid drop model | liquid drop model | neutron life cycle | neutron life cycle | criticality | criticality | accidents | accidents | neutron flux | neutron flux | neutron current | neutron current | neutron diffusion theory | neutron diffusion theory | elastic neutron scattering | elastic neutron scattering | group diffusion method | group diffusion method | subcritical multiplication | subcritical multiplication | point kinetics | point kinetics | dynamic period equation | dynamic period equation | inhour equation | inhour equation | shutdown margin | shutdown margin

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.251 Systems Analysis of the Nuclear Fuel Cycle (MIT) 22.251 Systems Analysis of the Nuclear Fuel Cycle (MIT)

Description

This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Also covered are the principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers. This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Also covered are the principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers.

Subjects

nuclear fuel | nuclear fuel | core design criteria | core design criteria | in-core aspects | in-core aspects | nuclear fuel cycle | nuclear fuel cycle | operations | operations | economics | economics | fast reactors | fast reactors | CANDU physics | CANDU physics | fuel cycle | fuel cycle | coupled reactor analysis | coupled reactor analysis | fuel manufacturing and design | fuel manufacturing and design | thorium fuel cycles | thorium fuel cycles

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.312 Engineering of Nuclear Reactors (MIT) 22.312 Engineering of Nuclear Reactors (MIT)

Description

This course covers the engineering principles of nuclear reactors, emphasizing power reactors. Specific topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. It also discusses engineering considerations in reactor design. This course covers the engineering principles of nuclear reactors, emphasizing power reactors. Specific topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. It also discusses engineering considerations in reactor design.

Subjects

power | power | reactors | reactors | thermodynamics | thermodynamics | heat generation and removal | heat generation and removal | coolant flow | coolant flow | single-phase coolant flow | single-phase coolant flow | two-phase coolant flow | two-phase coolant flow | reactor design | reactor design | structural mechanics | structural mechanics

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.313J Thermal Hydraulics in Power Technology (MIT) 22.313J Thermal Hydraulics in Power Technology (MIT)

Description

This course covers the thermo-fluid dynamic phenomena and analysis methods for conventional and nuclear power stations. Specific topics include: kinematics and dynamics of two-phase flows; steam separation; boiling, instabilities, and critical conditions; single-channel transient analysis; multiple channels connected at plena; loop analysis including single and two-phase natural circulation; and subchannel analysis. This course covers the thermo-fluid dynamic phenomena and analysis methods for conventional and nuclear power stations. Specific topics include: kinematics and dynamics of two-phase flows; steam separation; boiling, instabilities, and critical conditions; single-channel transient analysis; multiple channels connected at plena; loop analysis including single and two-phase natural circulation; and subchannel analysis.

Subjects

reactor | reactor | nuclear reactor | nuclear reactor | thermal behavior | thermal behavior | hydraulic | hydraulic | hydraulic behavior | hydraulic behavior | heat | heat | modeling | modeling | steam | steam | stability | stability | instability | instability | thermo-fluid dynamic phenomena | thermo-fluid dynamic phenomena | single-heated channel-transient analysis | single-heated channel-transient analysis | Multiple-heated channels | Multiple-heated channels | Loop analysis | Loop analysis | single and two-phase natural circulation | single and two-phase natural circulation | Kinematics | Kinematics | two-phase flows | two-phase flows | subchannel analysis | subchannel analysis | Core thermal analysis | Core thermal analysis

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses-energy.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.312 Engineering of Nuclear Reactors (MIT) 22.312 Engineering of Nuclear Reactors (MIT)

Description

This course covers the engineering principles of nuclear reactors, emphasizing power reactors. Specific topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. It also discusses engineering considerations in reactor design. This course covers the engineering principles of nuclear reactors, emphasizing power reactors. Specific topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. It also discusses engineering considerations in reactor design.

Subjects

power | power | reactors | reactors | thermodynamics | thermodynamics | heat generation and removal | heat generation and removal | coolant flow | coolant flow | single-phase coolant flow | single-phase coolant flow | two-phase coolant flow | two-phase coolant flow | reactor design | reactor design | structural mechanics | structural mechanics

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allsimplifiedchinesecourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

20.320 Analysis of Biomolecular and Cellular Systems (MIT) 20.320 Analysis of Biomolecular and Cellular Systems (MIT)

Description

This course focuses on computational and experimental analysis of biological systems across a hierarchy of scales, including genetic, molecular, cellular, and cell population levels. The two central themes of the course are modeling of complex dynamic systems and protein design and engineering. Topics include gene sequence analysis, molecular modeling, metabolic and gene regulation networks, signal transduction pathways and cell populations in tissues. Emphasis is placed on experimental methods, quantitative analysis, and computational modeling. This course focuses on computational and experimental analysis of biological systems across a hierarchy of scales, including genetic, molecular, cellular, and cell population levels. The two central themes of the course are modeling of complex dynamic systems and protein design and engineering. Topics include gene sequence analysis, molecular modeling, metabolic and gene regulation networks, signal transduction pathways and cell populations in tissues. Emphasis is placed on experimental methods, quantitative analysis, and computational modeling.

Subjects

biological engineering | biological engineering | kinase | kinase | PyMOL | PyMOL | PyRosetta | PyRosetta | MATLAB | MATLAB | Michaelis-Menten | Michaelis-Menten | bioreactor | bioreactor | bromodomain | bromodomain | protein-ligand interactions | protein-ligand interactions | titration analysis | titration analysis | fractional separation | fractional separation | isothermal titration calorimetry | isothermal titration calorimetry | ITC | ITC | mass spectrometry | mass spectrometry | MS | MS | co-immunoprecipitation | co-immunoprecipitation | Co-IP | Co-IP | Forster resonance energy transfer | Forster resonance energy transfer | FRET | FRET | primary ligation assay | primary ligation assay | PLA | PLA | surface plasmon resonance | surface plasmon resonance | SPR | SPR | enzyme kinetics | enzyme kinetics | kinase engineering | kinase engineering | competitive inhibition | competitive inhibition | epidermal growth factor receptor | epidermal growth factor receptor | mitogen-activated protein kinase | mitogen-activated protein kinase | MAPK | MAPK | genome editing | genome editing | Imatinib | Imatinib | Gleevec | Gleevec | Glivec | Glivec | drug delivery | drug delivery | kinetics of molecular processes | kinetics of molecular processes | dynamics of molecular processes | dynamics of molecular processes | kinetics of cellular processes | kinetics of cellular processes | dynamics of cellular processes | dynamics of cellular processes | intracellular scale | intracellular scale | extracellular scale | extracellular scale | and cell population scale | and cell population scale | biotechnology applications | biotechnology applications | gene regulation networks | gene regulation networks | nucleic acid hybridization | nucleic acid hybridization | signal transduction pathways | signal transduction pathways | cell populations in tissues | cell populations in tissues | cell populations in bioreactors | cell populations in bioreactors | experimental methods | experimental methods | quantitative analysis | quantitative analysis | computational modeling | computational modeling

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.312 Engineering of Nuclear Reactors (MIT) 22.312 Engineering of Nuclear Reactors (MIT)

Description

Engineering principles of nuclear reactors, emphasizing power reactors. Topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), structural mechanics, and engineering considerations in reactor design. Engineering principles of nuclear reactors, emphasizing power reactors. Topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), structural mechanics, and engineering considerations in reactor design.

Subjects

power | power | nuclear reactor | nuclear reactor | energy | energy | thermodynamics | thermodynamics | heat generation and removal | heat generation and removal | coolant flow | coolant flow | single-phase coolant flow | single-phase coolant flow | two-phase coolant flow | two-phase coolant flow | reactor design | reactor design | structural mechanics | structural mechanics

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.39 Integration of Reactor Design, Operations, and Safety (MIT)

Description

This course integrates studies of engineering sciences, reactor physics and safety assessment into nuclear power plant design. Topics include materials issues in plant design and operations, aspects of thermal design, fuel depletion and fission-product poisoning, and temperature effects on reactivity, safety considerations in regulations and operations, such as the evolution of the regulatory process, the concept of defense in depth, General Design Criteria, accident analysis, probabilistic risk assessment, and risk-informed regulations.

Subjects

nuclear reactor | nuclear power | NRC | PWR | pressurized water reactor | GFR | LWR | light water reactor | nuclear safety | meltdown | nuclear risk | PRA | probabalistic risk assessment | risk assessment | thermal | hydraulic | nuclear fuel | nuclear waste | accident | radiation radioactivity | nuclear plant | cooling Seabrook | fission | uranium | half-life | plutonium | economics of nuclear power | materials slection | IRIS | materials selection

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see https://ocw.mit.edu/terms/index.htm

Site sourced from

https://ocw.mit.edu/rss/all/mit-allcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.033 Nuclear Systems Design Project (MIT) 22.033 Nuclear Systems Design Project (MIT)

Description

Group design project involving integration of nuclear physics, particle transport, control, heat transfer, safety, instrumentation, materials, environmental impact, and economic optimization. Provides students with opportunity to synthesize knowledge acquired in nuclear and non-nuclear subjects and apply this knowledge to practical problems of current interest in nuclear applications design. Past projects have included using a fusion reactor for transmutation of nuclear waste, design and development of a nuclear reactor for the manned mission to Mars. Meets with graduate subject 22.33. Group design project involving integration of nuclear physics, particle transport, control, heat transfer, safety, instrumentation, materials, environmental impact, and economic optimization. Provides students with opportunity to synthesize knowledge acquired in nuclear and non-nuclear subjects and apply this knowledge to practical problems of current interest in nuclear applications design. Past projects have included using a fusion reactor for transmutation of nuclear waste, design and development of a nuclear reactor for the manned mission to Mars. Meets with graduate subject 22.33.

Subjects

team design project | team design project | nuclear engineering | nuclear engineering | pebble bed reactors | pebble bed reactors | critical parameters | critical parameters

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

8.21 The Physics of Energy (MIT) 8.21 The Physics of Energy (MIT)

Description

This course is designed to give you the scientific understanding you need to answer questions like:How much energy can we really get from wind?How does a solar photovoltaic work?What is an OTEC (Ocean Thermal Energy Converter) and how does it work?What is the physics behind global warming?What makes engines efficient?How does a nuclear reactor work, and what are the realistic hazards?The course is designed for MIT sophomores, juniors, and seniors who want to understand the fundamental laws and physical processes that govern the sources, extraction, transmission, storage, degradation, and end uses of energy.Special note about this course: The Physics of Energy is a new subject at MIT, offered for the first time in the Fall of 2008. The materials for the course, as such, are not yet ready fo This course is designed to give you the scientific understanding you need to answer questions like:How much energy can we really get from wind?How does a solar photovoltaic work?What is an OTEC (Ocean Thermal Energy Converter) and how does it work?What is the physics behind global warming?What makes engines efficient?How does a nuclear reactor work, and what are the realistic hazards?The course is designed for MIT sophomores, juniors, and seniors who want to understand the fundamental laws and physical processes that govern the sources, extraction, transmission, storage, degradation, and end uses of energy.Special note about this course: The Physics of Energy is a new subject at MIT, offered for the first time in the Fall of 2008. The materials for the course, as such, are not yet ready fo

Subjects

energy | energy | solar energy | solar energy | wind energy | wind energy | nuclear energy | nuclear energy | biological energy sources | biological energy sources | thermal energy | thermal energy | eothermal power | eothermal power | ocean thermal energy conversion | ocean thermal energy conversion | hydro power | hydro power | climate change | climate change | energy storage | energy storage | energy conservation | energy conservation | nuclear radiation | nuclear radiation | solar photovoltaic | solar photovoltaic | OTEC | OTEC | nuclear reactor | nuclear reactor

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.351 Systems Analysis of the Nuclear Fuel Cycle (MIT) 22.351 Systems Analysis of the Nuclear Fuel Cycle (MIT)

Description

In-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors are presented. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers. In-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors are presented. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers.

Subjects

nuclear fuel cycle | nuclear fuel cycle | uranium supply | uranium supply | enrichment fuel fabrication | enrichment fuel fabrication | in-core physics | in-core physics | fuel cycle economics | fuel cycle economics | applied reactor physics | applied reactor physics | Nonproliferation aspects | Nonproliferation aspects | disposal of excess weapons plutonium | disposal of excess weapons plutonium | transmutation of actinides | transmutation of actinides | fission products | fission products | spent fuel | spent fuel

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

1.85 Water and Wastewater Treatment Engineering (MIT) 1.85 Water and Wastewater Treatment Engineering (MIT)

Description

This course is an overview of engineering approaches to protecting water quality with an emphasis on fundamental principals. Theory and conceptual design of systems for treating municipal wastewater and drinking water are discussed, as well as reactor theory, process kinetics, and models. Physical, chemical, and biological processes are presented, including sedimentation, filtration, biological treatment, disinfection, and sludge processing. Finally, there is discussion of engineered and natural processes for wastewater treatment.Technical RequirementsMicrosoft® Excel software is recommended for viewing the .xls files found on this course site. Free Microsoft® Excel viewer software can also be used to view the .xls files. This course is an overview of engineering approaches to protecting water quality with an emphasis on fundamental principals. Theory and conceptual design of systems for treating municipal wastewater and drinking water are discussed, as well as reactor theory, process kinetics, and models. Physical, chemical, and biological processes are presented, including sedimentation, filtration, biological treatment, disinfection, and sludge processing. Finally, there is discussion of engineered and natural processes for wastewater treatment.Technical RequirementsMicrosoft® Excel software is recommended for viewing the .xls files found on this course site. Free Microsoft® Excel viewer software can also be used to view the .xls files.

Subjects

water pollution | water pollution | wastewater treatment | wastewater treatment | chemical treatment | chemical treatment | gas transfer | gas transfer | reactor tanks | reactor tanks | water quality | water quality | trickling filters | trickling filters | sludge handling | sludge handling | wastewater screening | wastewater screening

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.312 Engineering of Nuclear Reactors (MIT) 22.312 Engineering of Nuclear Reactors (MIT)

Description

Engineering principles of nuclear reactors, emphasizing power reactors. Power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. Engineering considerations in reactor design. Engineering principles of nuclear reactors, emphasizing power reactors. Power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. Engineering considerations in reactor design.

Subjects

reactor heat generation | reactor heat generation | Power plant thermodynamics | Power plant thermodynamics | Nuclear physics | Nuclear physics | nuclear energy | nuclear energy

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allarchivedcourses.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata

22.033 Nuclear Systems Design Project (MIT) 22.033 Nuclear Systems Design Project (MIT)

Description

This capstone course is a group design project involving integration of nuclear physics, particle transport, control, heat transfer, safety, instrumentation, materials, environmental impact, and economic optimization. It provides opportunities to synthesize knowledge acquired in nuclear and non-nuclear subjects and apply this knowledge to practical problems of current interest in nuclear applications design. Each year, the class takes on a different design project; this year, the project is a power plant design that ties together the creation of emission-free electricity with carbon sequestration and fossil fuel displacement. Students taking graduate version complete additional assignments.This course is an elective subject in MIT’s undergraduate Energy Studies Minor. This Institut This capstone course is a group design project involving integration of nuclear physics, particle transport, control, heat transfer, safety, instrumentation, materials, environmental impact, and economic optimization. It provides opportunities to synthesize knowledge acquired in nuclear and non-nuclear subjects and apply this knowledge to practical problems of current interest in nuclear applications design. Each year, the class takes on a different design project; this year, the project is a power plant design that ties together the creation of emission-free electricity with carbon sequestration and fossil fuel displacement. Students taking graduate version complete additional assignments.This course is an elective subject in MIT’s undergraduate Energy Studies Minor. This Institut

Subjects

nuclear energy | nuclear energy | reactor design | reactor design | design optimization | design optimization | biofuel | biofuel | carbon sequestration | carbon sequestration

License

Content within individual OCW courses is (c) by the individual authors unless otherwise noted. MIT OpenCourseWare materials are licensed by the Massachusetts Institute of Technology under a Creative Commons License (Attribution-NonCommercial-ShareAlike). For further information see http://ocw.mit.edu/terms/index.htm

Site sourced from

http://ocw.mit.edu/rss/all/mit-allcourses-energy.xml

Attribution

Click to get HTML | Click to get attribution | Click to get URL

All metadata

See all metadata