scholarly journals Federal look at the needs for energy-related materials research and development. Part I: near-term program. Appendix 2: nuclear energy panel report. Part 2A: details of current materials R and D programs to support LWR. Part 2B: seizing opportunities for international cooperation and collaboration. Part 2C: national alloy development program

1976 ◽  
Author(s):  
Not Given Author
Keyword(s):  
Research And Development ◽  
International Cooperation ◽  
Nuclear Energy ◽  
Development Program ◽  
Alloy Development ◽  
Panel Report ◽  
R And D ◽  
Materials Research ◽  
Near Term ◽  
Alloy Development Program

scholarly journals Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

2007 ◽  
Author(s):  
G.O. Hayner ◽  
R.L. Bratton ◽  
R.E. Mizia ◽  
W.E. Windes ◽  
W.R. Corwin ◽  
...  
Keyword(s):  
Research And Development ◽  
Development Program ◽  
Nuclear Plant ◽  
Next Generation ◽  
Plant Materials ◽  
Materials Research ◽  
Program Plan

High Resolution Sem Fractography of Te-Embrittled Hastelloy-N

1976 ◽  
Vol 34 ◽  
pp. 458-459
Author(s):  
D. N. Braski
Keyword(s):  
High Resolution ◽  
Grain Boundary ◽  
Molten Salt ◽  
Room Temperature ◽  
Development Program ◽  
Alloy Development ◽  
Fission Process ◽  
X Ray ◽  
Grain Boundary Embrittlement ◽  
Alloy Development Program

Hastelloy-N (16%Mo-7%Cr-4%Fe-0.55%Mn-0.06%C-bal Ni) has long been a leading candidate material for a molten salt reactor. However, it was recently discovered that small amounts of Te, created by the fission process, caused grain boundary embrittlement in the structural material. Consequently, an alloy development program at this laboratory has directed considerable efforts towards modification of Hastelloy-N to improve its resistance to Te embrittlement and still retain excellent resistance to radiation damage. In this investigation, a JEOL 100C TEM with an energy dispersive x-ray spectrometer (EDX) and high resolution (50 Å) SEM attachments have been used to characterize the grain boundary surfaces of various Hastelloy-N alloys embrittled by Te.Samples of Hastelloy-N were exposed to the tellurium source, Cr3Te4, in a molten salt (LiF + BeF2 + ThF4) or to the vapor above Cr3Te4 in a closed quartz system. All corrosion tests were at 700°C. The samples were subsequently tensile tested to failure at room temperature.

Multispecimen Fatigue Crack Propagation Testing

1981 ◽  
Vol 103 (3) ◽  
pp. 240-245 ◽  
Author(s):  
A. M. Ermi ◽  
R. E. Bauer ◽  
B. A. Chin ◽  
J. L. Straalsund
Keyword(s):  
Fatigue Crack ◽  
Crack Propagation ◽  
Fatigue Crack Propagation ◽  
Testing Machine ◽  
Electrical Potential ◽  
Development Program ◽  
Test Methods ◽  
Alloy Development ◽  
Cold Worked ◽  
Alloy Development Program

Chains of miniature center-cracked-tension specimens were tested on a conventional testing machine and on a prototypic in-reactor fatigue machine as part of the fusion reactor materials alloy development program. Annealed and 20 percent cold-worked 316 stainless steel specimens were cycled under various conditions of temperature, frequency, stress ratio and chain length. Crack growth rates determined from multispecimen visual measurements and from an electrical potential technique were consistent with those obtained by conventional test methods. Results demonstrate that multispecimen chain testing is a valid method of obtaining fatigue crack propagation information for alloy development.

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