Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl

Flow Blockage Accident Analysis of Tehran Research Reactor Fuel Assembly

Tehran Research Reactor (T.R.R.) is a pool-type, 5 MW thermal research reactor. One probable event is that if some external objects or debris fall down into the reactor core and cause obstruction of the coolant flow through one of the fuel assemblies, decreasing the surface flow area, ceases the coolant flow, and also raises the fuel and sheaths tempe...

Thermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings

The thermophysical performance and solid mechanics behavior of UO2-36.4vol % BeO fuel pellets cladded with Zircaloy, SiC, and FeCrAl, and Zircaloy cladding materials coated with SiC and FeCrAl, are investigated based on simulation results obtained by the CAMPUS code. In addition, the effect of coating thickness (0.5, 1 and 1.5 mm) on fuel performance and mechanical interaction is discussed. The...

Behaviors of Nuclear Fuel Cladding During RIA

Recycle of Zirconium from Used Nuclear Fuel Cladding:

Feasibility tests were initiated to determine if the zirconium in commercial used nuclear fuel (UNF) cladding can be recovered in sufficient purity to permit re-use, and if the recovery process can be operated economically. Initial tests are being performed with unirradiated, non-radioactive samples of various types of Zircaloy materials that are used in UNF cladding to develop the recovery pro...

Characteristics of Hydride Precipitation and Reorientation in Spent-fuel Cladding*

The submitted manuscript has been created by the University of Chicago as Operator of Argonne National Laboratory ~Argonne”) under Contract No. W-3 1109ENG-38 with the U.S. Department of Energy. The U.S. Government retains for itself, snd others acting on its behalf, a paid-up, nonexclusive, irrevocable worldwide license in ssid article to reproduce, prepare derivative works, distribute copies ...