Material Selection for Accident Tolerant Fuel Cladding

Behaviors of Nuclear Fuel Cladding During RIA

A Common Weight Data Envelopment Analysis Approach for Material Selection

Material selection is one of the major problems in manufacturing environments since the improper selected material may lead to fail in the production processes and result in customer dissatisfaction and cost inefficiency. Every material has different properties which should be considered as major criteria during the material selection procedure. Selection criteria could be quantitative or quali...

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 ...

Nuclear fuel in a reactor accident.

Nuclear accidents that lead to melting of a reactor core create heterogeneous materials containing hundreds of radionuclides, many with short half-lives. The long-lived fission products and transuranium elements within damaged fuel remain a concern for millennia. Currently, accurate fundamental models for the prediction of release rates of radionuclides from fuel, especially in contact with wat...