Irradiated fuel cladding scraps produced in reprocessing plants constitute contaminated and irradiating nuclear waste. While the cement embedding method currently used to condition such wastes is simple and inexpensive, an alternative method for conditioning zircaloy and stainless steel cladding wastes has been developed in France by the Commissariat a l`Energie Atomique (CEA) at Marcoule since 1982. The volume reduction factor is maximized and the final product is chemically stable, with a small potential leaching exchange surface area, and contains no tritium. Under some circumstances the decontaminating effect may be sufficient to allow storage under less stringent conditions. A nonradioactive industrial prototype has been built and qualified. Since 1988, a lab-scale hot-cell unit has also demonstrated process feasibility with actual radioactive clads while providing essential process data on volatilization and decontamination factors. A full-scale radioactive industrial prototype has been built in the Pilot Reprocessing Facility at Marcoule and should begin operation in 1992.