|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||Microstructural Investigations of Temperature Effects in Reactor Pressure Vessel Steels from the UCSB ATR-2 Irradiation
||Nathan Almirall, Peter Wells, Takuya Yamamoto, David Gragg, Kirk Fields, G. R. Odette, Randy Nanstad, Keith Wilford, Tim Williams, Lynne Ecker, David Sprouster
|On-Site Speaker (Planned)
Light water reactor life-extension is critical to continuing nuclear power’s C-free contribution to ≈20% of our electricity supply. However, it is absolutely necessary to show that the reactor pressure vessel (RPV) continues to maintain very large safety margins during extended life, in the face of irradiation embrittlement, manifested as increases in the ductile-to-brittle transition temperature, (TTS). One of the goals of the UCSB ATR-2 irradiation experiment is to support development of physically based models of TTS for high-fluence-low flux conditions (φt >1020 n/cm2, >1 MeV, φ < 1011 n/cm2-s) seen by RPVs at 80 year extended lifetimes. This presentation covers the effects of lower Tirr=250C on the size <d>, number density N, and volume fraction fv of embrittling Mn-Ni-Si precipitates (MNSPs). A wide range of techniques were used including atom probe tomography (APT); (b) small angle neutron scattering (SANS); (c) small angle x-ray scattering (SAXS) and X-ray diffraction (XRD).
||Planned: Supplemental Proceedings volume