Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I)

The Advanced Test Reactor National Scientific User Facility (ATR NSUF) and Electric Power Research Institute (EPRI) formed an agreement to test representative alloys used as reactor structural materials as a pilot program toward establishing guidelines for future ATR NSUF research programs. This report contains results from the portion of this program established as Phase I (of three phases) that entails baseline fracture toughness, stress corrosion cracking (SCC), and tensile testing of selected materials for comparison to similar tests conducted at GE Global Research. The intent of this Phase I research program is to determine baseline properties for the materials of interest prior to irradiation, and to ensure comparability between laboratories using similar testing techniques, prior to applying these techniques to the same materials after having been irradiated at the Advanced Test Reactor (ATR). The materials chosen for this research are the nickel based super alloy X-750, and nitrogen strengthened austenitic stainless steel XM-19. A spare core shroud upper support bracket of alloy X-750 was purchased by EPRI from Southern Co. and a section of XM-19 plate was purchased by EPRI from GE-Hitachi. These materials were sectioned at GE Global Research and provided to INL

Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I)

The Advanced Test Reactor National Scientific User Facility (ATR NSUF) and Electric Power Research Institute (EPRI) formed an agreement to test representative alloys used as reactor structural materials as a pilot program toward establishing guidelines for future ATR NSUF research programs. This report contains results from the portion of this program established as Phase I (of three phases) that entails baseline fracture toughness, stress corrosion cracking (SCC), and tensile testing of selected materials for comparison to similar tests conducted at GE Global Research. The intent of this Phase I research program is to determine baseline properties for the materials of interest prior to irradiation, and to ensure comparability between laboratories using similar testing techniques, prior to applying these techniques to the same materials after having been irradiated at the Advanced Test Reactor (ATR). The materials chosen for this research are the nickel based super alloy X-750, and nitrogen strengthened austenitic stainless steel XM-19. A spare core shroud upper support bracket of alloy X-750 was purchased by EPRI from Southern Co. and a section of XM-19 plate was purchased by EPRI from GE-Hitachi. These materials were sectioned at GE Global Research and provided to INL

Comprehensive hygro-thermo-mechanical modeling and testing of stacked die BGA module with molded underfill

Proceedings - Electronic Components and Technology Conference1196-200PECC

Hygro-thermo-mechanical modeling of mixed flip-chip and wire bond stacked die BGA module with molded underfill

Proceedings of 6th Electronics Packaging Technology Conference, EPTC 2004630-63

Arch Gerontol Geriatr

BACKGROUND: The decline in lean mass, observed in older people, has been frequently associated with frailty. This assumption has scarcely been assessed. This study explored the association between current proposed definitions of low lean mass and the Fried phenotype of frailty. METHODS: Cross-sectional study. Participants admitted to the Toulouse frailty day hospital, with an assessment of body composition, 70 years or older were included consecutively in the study. Low lean mass (LLM), was identified using five international operative definitions. To construct the definitions, muscle mass was assessed using Intelligent Dual Energy X-ray absorptiometry (I-DXA, LUNAR). Frailty was assessed using the Fried criteria. RESULTS: Data from 283 participants, mean age 82 years and 71% of women were analyzed. LLM was identified between 8.5% and 39.2% of the participants according to the different definitions. Frailty was identified in 46.6% of the sample. 9.1%-48.5% of the frail older people had LLM depending on the definition. The highest association between frailty and LLM was observed with the definition proposed by the Foundation for the National Institutes of Health (FNIH) Sarcopenia Project [adjusted Odds Ratio 2.64; 95% confidence interval 1.5-4.8]. CONCLUSION: The decline in lean mass is a component of the frailty syndrome but not universally present. Indeed, LLM and frailty were associated and partly overlapped. Future research including longitudinal studies should exploit the added value of combining LLM and frailty measures in preventing disability and other negative health outcomes

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production

The supercritical water reactor (SCWR) has been the object of interest throughout the nuclear Generation IV community because of its high potential: a simple, direct cycle, compact configuration; elimination of many traditional LWR components, operation at coolant temperatures much higher than traditional LWRs and thus high thermal efficiency. It could be said that the SWR was viewed as the water counterpart to the high temperature gas reactor