Sentence examples for fuel rod cladding from inspiring English sources

The operational experience and measurement results of fuel rod cladding leak tightness control system are presented.

A model of nuclear reactor fuel rod cladding failure estimation under multiple cyclic power changes is proposed.

Especially, fretting of fuel rod cladding material, zircaloy-4 tube, in pressurized water reactor (PWR) must be reduced and avoided.

These include the Department of Energy-sponsored Consortium for Advanced Modeling of Light-Water Reactors, which is focused primarily on nuclear fuel-related challenges, including fuel rod cladding – the slender tubes that hold fuel pellets while they are in use in fission reactors.

Therefore, in this study a fretting wear experiment was performed using TiN coated zircaloy-4 tube as the fuel rod cladding material and uncoated zircaloy-4 tube as one of the grids.

Following this thermo-mechanical analysis, a best-estimate and parametric examination of SiC/SiC fuel rod cladding structures has been performed using appropriate Weibull statistics to prescribe basic design guidelines and to begin to define a probable design space.

It is found that all results including fuel rods, cladding, and coolant exit temperature are below the safety limit of general SFR design criteria.

The design takes advantage of the high heavy metal ratio, high melting point and high thermal conductivity of the UN fuel, and uses HT-9 stainless steel for the UN fuel rods cladding, the core structure, and the reactor primary and guard vessels.

Zirconium is a good nuclear fuel-rod cladding metal, with the desirable properties of a very low neutron capture cross-section and good chemical stability at high temperatures.

This was done to cool fuel rods and cladding as they emerged from reactors heated to hundreds of degrees celsius.

Thermo-mechanical behaviors of supercritical pressure light water cooled fast reactor (SWFR) fuel rod and cladding have been investigated by FEMAXI-6 (Ver.1) code with high enriched MOX fuel at elevated operating condition of high coolant system pressure (25 MPa) and high temperature (500 °C in core average outlet temperature).