Evaluation of Risk From Carbon Macro-Segregation in Large Pressure Retaining Forged Nuclear Components

Autor: Ronald Gamble, Timothy Hardin

Publikováno v: Volume 6B: Materials and Fabrication.

Regions of higher-than-normal carbon content due to carbon macro-segregation have been found in large, pressure retaining forged ferritic steel components in some nuclear reactors. Higher carbon content in ferritic steel can decrease the resistance t

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a7c78bd1d5a2c06fde34a98a69d28317
https://doi.org/10.1115/pvp2018-84620

Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels

Autor: Benjamin E. Mays, Takuya Ogawa, Timothy Hardin, J. Brian Hall

Publikováno v: Volume 7: Operations, Applications and Components.

Current USA regulations in 10 CFR 50, Appendices G & H ensure adequate fracture toughness and provide for the monitoring of radiation embrittlement of the ferritic components of the reactor pressure vessel (RV). Regulatory Guide (RG) 1.99, Rev. 2 pro

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::247020dbce0e83d2a5fbbb8e1319e8ea
https://doi.org/10.1115/pvp2017-65317

U.S. High Fluence Power Reactor Surveillance Data—Past and Future

Autor: Randy K. Nanstad, Timothy Hardin, J. Brian Hall, William Server

Publikováno v: Journal of Pressure Vessel Technology. 136

Enhanced radiation embrittlement at high fluence, indicative of extended operating life beyond 60 years for current operating pressurized water reactor (PWR) vessels, has been identified as a potential limiting degradation mechanism. Currently, there

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::48b6622598f45e6fe01094fb139aba14
https://doi.org/10.1115/1.4026149

Proposed Coordinated U.S. PWR Reactor Vessel Surveillance Program: An Updated Summary Including Program Optimization

Autor: Dennis Weakland, Sarah Davidsaver, Ryan Hosler, Greg Troyer, Timothy Hardin

Publikováno v: Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors ISBN: 9783319487601
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Irradiated reactor pressure vessel (RPV) surveillance data is used to predict decreases in RPV fracture toughness due to irradiation embrittlement. A limited amount of data at fluences that many U.S. PWR RPVs will reach in 60 or more years of operati

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b5caf10bfa2a359bc14b9d4043d9a12a
https://doi.org/10.1007/978-3-319-48760-1_106

Leveraging the learning process in manufacturing

Autor: Ingle, Timothy H. (Timothy Hardin)

Thesis (M.S.)--Massachusetts Institute of Technology, Sloan School of Management, 1997, and Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1997.
Includes bibliographical references (p. 59-61).
by Timo

Externí odkaz: http://hdl.handle.net/1721.1/10473