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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

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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

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

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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

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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

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