|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||Mechanical and Microstructural Characterization of Some High Fluence Intermediate Flux Neutron Irradiated Reactor Pressure Vessel Steels
||Nathan Almirall, Peter Wells, Takuya Yamamoto, David Gragg, Kirk Fields, G. Robert Odette, Randy Nanstad, Keith Wilford, Ian Edmonds
|On-Site Speaker (Planned)
Extended operation of nuclear reactors to 80 years will require ensuring the integrity of reactor pressure vessels (RPV). RPV steels experience neutron irradiation-induced hardening and corresponding ductile brittle transition temperature shifts (TTS). The TTS must be predicted and safely managed. Some initial results from UCSB Advanced Test Reactor (ATR-2) neutron irradiation experiment (high fluence, intermediate flux) will be discussed. UCSB ATR-2 fills a critical gap in embrittlement data and understanding, especially since current models systematically underpredict TTS at high fluence. This talk will focus on mechanical (tensile tests) of a small subset of the extensive matrix of alloys and irradiation conditions in UCSB ATR-2 experiment. A particular focus will be on the effect of flux and fluence on the volume fraction, number density, average size, composition and character of precipitates and defect-solute complexes that form under irradiation.
||Planned: A print-only volume