George M. Jacobsen

TL;DR: In this article, mechanical and thermal properties of unirradiated, as-fabricated SiC-based cladding structures were measured, and permeability and dimensional control were assessed.

TL;DR: In this article, a new model was developed to calculate stresses and failure probabilities for multi-layer cladding consisting of SiC-based materials in reactor operating conditions, and the results showed that stresses in SiCbased cladding are dominated by temperature-dependent irradiation-induced swelling, with the largest stresses occurring during the cold shutdown conditions.

TL;DR: In this paper, the C-ring test is evaluated for use with nuclear grade SiC/SiC f as a method of measuring hoop strength for the samples tested in this work, hoop strengths from c-ring testing are shown to agree within 6% to those obtained using expanding plug testing and analysis shows that the expected composite behavior is observed during testing.

TL;DR: In this paper, a cylindrical SiC-SiC composite tube sealed with a butted scarf endplug provides out-of-pile strength and permeability performance that meets light water reactor design requirements.

TL;DR: In this paper, the authors report the mechanical strength of nuclear grade silicon carbide fiber reinforced SiCf-SiCm composites under several different stress states, including uniaxial tension, elastomer insert burst test, open and closed end hydraulic bladder burst test and torsion test.