Expanded plug method for developing circumferential...

Measuring and testing – Specimen stress or strain – or testing by stress or strain... – By loading of specimen

Reexamination Certificate

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Reexamination Certificate

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07140259

ABSTRACT:
A method for determining the circumferential properties of a tubular product, especially nuclear fuel cladding, utilizes compression of a polymeric plug within the tubular product to determine strain stress, yield stress and other properties. The process is especially useful in the determination of aging properties such as fuel rod embrittlement after long burn-down.

REFERENCES:
patent: 4004972 (1977-01-01), Mogard
patent: 4785675 (1988-11-01), Takasu et al.
patent: 4822559 (1989-04-01), Mogard
Daum et al., “Mechanical Properties of Irradiated Zircaloy—4 for Dry Cask Storage Conditions and Accidents”Nuclear Safety Research Conference, Washington DC (2003).
Daum et al. Mechanical Property Testing of Irradiated Zircalog Cladding Under Reactor Transient Conditions,:Small Specimen Test Techniques: Fourth Volume, ASTM STP 1418, M A Solokov, JD Landes and G E Lucas eds. ASTM West Conshohockey PA (2002) and Link et al., Nuclear Engineering and Design, 186, 379 (1998).
S. Uchikawa, “Ring Tinsile Testing of Zircaloy Cladding Tubes at JAERI”FSRM, Tokyo (2004) and ASTM D 2290-92 (1992).
Dufoumeaud et al, “Elastic-Plastic Deformation of a Nuclear Fuel Cladding Specimen Under the Internal Pressure of a Polymer Pellet”World Congress on Computational Mechanics, Vienna (2002).

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