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eBook Chapter

IWE and IWL

Book: Companion Guide to the ASME Boiler and Pressure Vessel Codes, Volume 2, Fifth Edition

Publisher: ASME Press

Published: 2018

DOI: https://doi.org/10.1115/1.861318_ch31

ISBN: 9780791861318

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Topics: Boiling water reactors, Concretes, Containment, Inspection, Leakage, Maintenance, Metals, Nuclear power stations, Pressure, Pressurized water reactors

eBook Chapter

Demonstrative Examples of the Component-Level Importance Measure

Book: Risk Importance Measures in the Design and Operation of Nuclear Power Plants

Publisher: ASME Press

Published: 2017

DOI: https://doi.org/10.1115/1.861394_ch10

ISBN: 9780791861394

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Topics: Computers, Nuclear power stations, Pressurized water reactors, Risk

eBook Chapter

Nuclear Reactor Safety Systems

Book: Nuclear Reactor Thermal-Hydraulics: Past, Present and Future

Publisher: ASME Press

Published: 2017

DOI: https://doi.org/10.1115/1.861288_ch3

ISBN: 9780791861288

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Topics: Emergency core cooling systems, Heat, Nuclear reactor safety, Nuclear reactors, Pressurized water reactors, Safety

eBook Chapter

Generation III+ PWRs

Book: Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards

Publisher: ASME Press

Published: 2014

DOI: https://doi.org/10.1115/1.860199_ch15

ISBN: 9780791860199

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Topics: Pressurized water reactors

eBook Chapter

PWR Reactor Vessel Integrity and Internals Aging Management

Book: Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards

Publisher: ASME Press

Published: 2014

DOI: https://doi.org/10.1115/1.860199_ch20

ISBN: 9780791860199

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Topics: Pressurized water reactors, Reactor vessels

eBook Chapter

PWR Reactor Vessel Alloy 600 Issues

Book: Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards

Publisher: ASME Press

Published: 2014

DOI: https://doi.org/10.1115/1.860199_ch21

ISBN: 9780791860199

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Topics: Alloys, Pressurized water reactors, Reactor vessels

eBook Chapter

Evolution of Containment Systems for Gen III Reactors

Book: Containment Structures of U.S. Nuclear Power Plants: Background, Regulations, Codes and Standards, and Other Considerations

Publisher: ASME Press

Published: 2013

DOI: https://doi.org/10.1115/1.860175_ch9

ISBN: 9780791860175

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Topics: Accidents, Boiling water reactors, Construction, Containment systems, Licensing, Pressurized water reactors, Safety

eBook Chapter

Iwe and Iwl

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Fourth Edition

Publisher: ASME Press

Published: 2012

DOI: https://doi.org/10.1115/1.859872.ch31

ISBN: 9780791859872

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Topics: Boiling water reactors, Concretes, Containment, Inspection, Leakage, Maintenance, Metals, Nuclear power, Nuclear power stations, Pressure

eBook Chapter

PWR Reactor Vessel Integrity and Internals Aging Management

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition

Publisher: ASME Press

Published: 2009

DOI: https://doi.org/10.1115/1.802717.ch43

ISBN: 9780791802717

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Topics: Pressurized water reactors, Reactor vessels

eBook Chapter

PWR Reactor Vessel Alloy 600 Issues

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition

Publisher: ASME Press

Published: 2009

DOI: https://doi.org/10.1115/1.802717.ch44

ISBN: 9780791802717

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Topics: Alloys, Pressurized water reactors, Reactor vessels

eBook Chapter

Generation III+ PWRs

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition

Publisher: ASME Press

Published: 2009

DOI: https://doi.org/10.1115/1.802717.ch57

ISBN: 9780791802717

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Topics: Pressurized water reactors

eBook Chapter

Czech and Slovakian Codes

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition

Publisher: ASME Press

Published: 2009

DOI: https://doi.org/10.1115/1.802717.ch64

ISBN: 9780791802717

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Topics: ASME Standards, China, Design, Engineering standards, Governments, In-service inspection, Manufacturing, Mechanical engineers, Nuclear industry, Nuclear power

eBook Chapter

Development of Nuclear Boiler and Pressure Vessels in Taiwan

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition

Publisher: ASME Press

Published: 2009

DOI: https://doi.org/10.1115/1.802717.ch70

ISBN: 9780791802717

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Topics: Boilers, Boiling water reactors, Construction, Earthquake resistant design, Earthquakes, Inspection, Licensing, Measurement uncertainty, Metals, Nozzles

eBook Chapter

Subsection NG — Core Support Structures

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition

Publisher: ASME Press

Published: 2009

DOI: https://doi.org/10.1115/1.802694.ch11

ISBN: 9780791802694

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Topics: ASME Standards, Boiling water reactors, Building materials, Design, Fasteners, Inspection, Maintenance, Manufacturing, Materials degradation, Overpressure protection

eBook Chapter

Iwe and Iwl

Book: Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition

Publisher: ASME Press

Published: 2009

DOI: https://doi.org/10.1115/1.802700.ch30

ISBN: 9780791802700

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Topics: ASME Standards, Boiling water reactors, Concretes, Containment, Containment vessels, Corrosion, In-service inspection, Inspection, Leakage, Life extension

eBook Chapter

Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)

Book: Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)

Series: ASME Press Select Proceedings

Publisher: ASME Press

Published: 2006

DOI: https://doi.org/10.1115/1.802442.paper49

ISBN-10: 0791802442

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Topics: Accident management, Accidents, Boundary-value problems, Construction, Containment, Damage, Emergencies, Errors, Failure, Fire

eBook Chapter

Link between Level 2 PSA and Off-Site Emergency Preparedness (PSAM-0363)

Book: Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)

Series: ASME Press Select Proceedings

Publisher: ASME Press

Published: 2006

DOI: https://doi.org/10.1115/1.802442.paper51

ISBN-10: 0791802442

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Topics: Accidents, Countermeasures, Emergencies, Emergency management, Emergency preparedness, Emergency response, Modeling, Nuclear fission, Nuclear power stations, Pressurized water reactors

eBook Chapter

LOCA Frequencies Estimated from Operating Experience (PSAM-0282)

Book: Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)

Series: ASME Press Select Proceedings

Publisher: ASME Press

Published: 2006

DOI: https://doi.org/10.1115/1.802442.paper141

ISBN-10: 0791802442

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Topics: Accidents, Boiling water reactors, Coolants, Design, Light water reactors, Nuclear industry, Nuclear power stations, Pressurized water reactors, Probability, Regulations

eBook Chapter

Pre-Accidental Situations Highlighted by RECUPERARE Method and Data (PSAM-0029)

Book: Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)

Series: ASME Press Select Proceedings

Publisher: ASME Press

Published: 2006

DOI: https://doi.org/10.1115/1.802442.paper164

ISBN-10: 0791802442

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Topics: Delays, Errors, Failure, Feedback, Human reliability analysis, Pressurized water reactors, Probability, Weight (Mass)

eBook Chapter

Application of Probabilistic Methods for the Evaluation of Deterministic Deviations from Technical Specifications (PSAM-0277)

Book: Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)

Series: ASME Press Select Proceedings

Publisher: ASME Press

Published: 2006

DOI: https://doi.org/10.1115/1.802442.paper228

ISBN-10: 0791802442

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Topics: Accident management, Accidents, Cooling systems, Cross connections, Damage, Decision making, Design, Fittings, Nuclear power, Nuclear power stations

NARROW

IWE and IWL

Demonstrative Examples of the Component-Level Importance Measure

Nuclear Reactor Safety Systems

Generation III+ PWRs

PWR Reactor Vessel Integrity and Internals Aging Management

PWR Reactor Vessel Alloy 600 Issues

Evolution of Containment Systems for Gen III Reactors

Iwe and Iwl

PWR Reactor Vessel Integrity and Internals Aging Management

PWR Reactor Vessel Alloy 600 Issues

Generation III+ PWRs

Czech and Slovakian Codes

Development of Nuclear Boiler and Pressure Vessels in Taiwan

Subsection NG — Core Support Structures

Iwe and Iwl

Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)

Link between Level 2 PSA and Off-Site Emergency Preparedness (PSAM-0363)

LOCA Frequencies Estimated from Operating Experience (PSAM-0282)

Pre-Accidental Situations Highlighted by RECUPERARE Method and Data (PSAM-0029)

Application of Probabilistic Methods for the Evaluation of Deterministic Deviations from Technical Specifications (PSAM-0277)

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