Simulating the carbon distribution in zirconium alloy spent fuel cladding

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 ...

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...

Spent Fuel Reprocessing: an Overview

India has entered in the field of spent fuel reprocessing as early as sixties by way of R&D studies and finalising the process flow sheet. India's first spent fuel reprocessing plant was commissioned in the year 1965 at Trombay to reprocess spent fuel arising from research reactors. The recovered plutonium is being utilised to feed various programmes of the department. With the passage of time,...

Purification of Zirconium cladding using a chloride volatility process

The United States produces a large amount of cladding material from used nuclear fuel, expected to approach 1,000 MT/year for the next 50 year. This requires a technical route to manage this cladding material. Three approaches (mechanical, thermo-mechanical, chemical) were proposed to manage the radioactive cladding. In the mechanical approach, the cladding is compacted and stored with a cement...

Behaviors of Nuclear Fuel Cladding During RIA