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Mechanistic and Validated Creep/Fatigue Predictions for Alloy 709 from Accelerated Experiments and Simulations (Final Technical Report)

Technical Report ·
DOI:https://doi.org/10.2172/1581796· OSTI ID:1581796
 [1];  [2];  [2];  [3];  [4];  [5];  [2];  [2]
  1. North Carolina State Univ., Raleigh, NC (United States); North Carolina State University
  2. North Carolina State Univ., Raleigh, NC (United States)
  3. Argonne National Lab. (ANL), Argonne, IL (United States)
  4. Univ. of Alabama, Tuscaloosa, AL (United States); North Carolina State Univ., Raleigh, NC (United States)
  5. North Carolina State Univ., Raleigh, NC (United States); Atomic Energy Research Inst., Riyadh (Saudi Arabia)

As a promising candidate for fast reactor program, Alloy 709 possesses excellent high temperature thermo-mechanical properties. To support its qualification in the ASME code for Class 1 Components in Elevated Temperature Service (Section 3, Division 1, Subsection NH), it was proposed to develop mechanistic methods for predicting creep and creep-fatigue deformation rates based on accelerated in-situ and ex-situ tests, and mesoscale dislocation dynamics (DD) simulations.

Research Organization:
North Carolina State Univ., Raleigh, NC (United States); Ames Laboratory (AMES), Ames, IA (United States): Univ. of Alabama, Tuscaloosa, AL (United States); Atomic Energy Research Inst., Riyadh (Saudi Arabia)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
NE0008452
OSTI ID:
1581796
Report Number(s):
DOE-NCSU--15-8582; 15-8582
Country of Publication:
United States
Language:
English

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