scholarly journals Characterization of nuclear reactor containment penetrations. Final report

1985 ◽  
Author(s):  
M.H. Shackelford ◽  
T.R. Bump ◽  
R.W. Seidensticker
Keyword(s):  
Nuclear Reactor ◽  
Final Report

scholarly journals Characterization of Creep-Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components (Final Report)

2019 ◽  
Author(s):  
Gabriel Potirniche ◽  
Robert Stephens ◽  
Indrajit Charit ◽  
Nicholas Shaber ◽  
Jose Ramirez ◽  
...  
Keyword(s):  
Fatigue Crack ◽  
Fatigue Crack Growth ◽  
Crack Growth ◽  
Nuclear Reactor ◽  
Final Report ◽  
Creep Fatigue ◽  
Creep Fatigue Crack

Determination of the Hydrogen Concentration in Zr-2.5Nb Alloy by a Resonant Ultrasound Spectroscopy

2006 ◽  
Vol 321-323 ◽  
pp. 1576-1579
Author(s):  
Yong Moo Cheong ◽  
Young Suk Kim
Keyword(s):  
Hydrogen Concentration ◽  
Zirconium Alloy ◽  
Nuclear Reactor ◽  
Zirconium Alloys ◽  
Resonant Ultrasound Spectroscopy ◽  
Heavy Water Reactor ◽  
Resonant Ultrasound ◽  
Non Destructive

Zirconium alloys are used for many applications in nuclear components, such as the pressure tube material in a pressurized heavy water reactor, nuclear fuel cladding, etc. One of the problems during the operation of a nuclear reactor is the degradation of the zirconium alloys, which is due to an increase of the hydrogen content in the zirconium alloy. Therefore a non-destructive determination of the hydrogen concentration in zirconium alloy is one of the important issues that need to be addressed. The resonant ultrasound spectroscopy (RUS) technique is evaluated for a characterization of the hydrogen concentration in Zr-2.5Nb alloy. Referring to the terminal solid solubility for dissolution (TSSD) of Zr-2.5Nb alloy, the plot of the mechanical damping coefficient (Q-1) versus the temperature or the deviation of the resonant frequency for the temperature (df/dT) versus the temperature was correlated for the hydrogen concentration in Zr-2.5Nb alloy. It was found that the temperature at an abrupt change of the slope can be correlated with the hydrogen concentration of the Zr-2.5Nb alloy.

Characterizing noise barriers: SOPRANOISE half-term progress report

2021 ◽  
Vol 263 (3) ◽  
pp. 3663-3674
Author(s):  
Jean-Pierre Clairbois ◽  
Massimo Garai ◽  
Wolfram Bartolomaeus ◽  
Michael Chudalla ◽  
Fabio Strigari ◽  
...  
Keyword(s):  
Test Methods ◽  
Progress Report ◽  
Physical Significance ◽  
Final Report ◽  
Noise Barriers ◽  
Railway Noise ◽  
Development Phases ◽  
Effective Use

SOPRANOISE targets simplified assessment of the in-situ intrinsic acoustic performances of road / railway noise barriers. This paper presents its half-term progress. The research is divided in 5 Work Packages, the scientific ones being WP2 to WP5.WP2 is about establishing a state of art (SoA) of the intrinsic performances characterization: it is now finished and presented in 2 other papers by Conter and Fuchs. WP3 is about in-situ inspection tools: based on a review / questionnaire, an inspection protocol has been developed allowing simplified assessments mainly based on visual inspections and characterization of possible defects; WP3 is now in its final testing phase. WP4 is about designing a brand new "quick and safe methods" that could take place "in between" the inspection tools and the standardized EN1793-5 and 6; the research and development phases of WP4 are now finished, while its validation along highways is now scheduled. Finally, WP5 is about the use of noise barriers in the European market and the final report: a synthesis on the physical behavior of noise barriers and the physical significance of the test methods has been done, as well a SoA on the effective use of noise barriers; the results will be presented.

Characterization of radiation hardened fibers in a research grade nuclear reactor

2021 ◽  
Author(s):  
Garry Berkovic ◽  
Shlomi Zilberman ◽  
Ehud Shafir ◽  
Yosef London ◽  
M. Dadon ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Radiation Hardened ◽  
Research Grade
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