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Tensile tests of claddings with hydrogen containing bands showed simultaneous cladding tube ruptures at these bands below and above the burst opening.
During nuclear reactor operation, the inner side of the zircaloy cladding tube is implanted by recoil with fission products.
Ferritic/martensitic steels with Cr of 9% – 12% (in mass percent) are favourable candidates for fuel cladding tube and in-core components of supercritical water-cooled reactor.
As a long-term national research project, advanced radiation resistant oxide dispersion strengthened steel (ARROS) is being developed as an in-core fuel cladding tube material for a SFR in the future.
Axial and tangential tensile tests were performed on as-received and machined fuel cladding tube samples of both E110 and E110G Russian zirconium alloys at room temperature to compare their ultimate tensile strengths and the different sample preparation methods.
This paper explores a simple model of a light water reactor nuclear fuel rod, which consists of cylindrical pellets of uranium dioxide (UO2) fuel sealed within a Zircalloy cladding tube.
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Cladding tubes are structural parts of nuclear plants, submitted to complex thermomechanical loadings.
Experimental evaluation of plastic shearing due to cold rolling Zircaloy-4 (Zy4) cladding tubes has been performed.
Cladding tubes encapsulate radioactive fuel pellets and isolate them and other harmful fission products from the surrounding environment by providing physical barrier.
The specimens are fabricated from cladding tubes made of austenitic stainless steel for Indian fast breeder reactors.
Neutron radiography of cladding tubes showed that at the inner rod simulator group so called secondary hydriding occurred.
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