No abstract available

[en] Research in France on the solidification of high-level waste, that is, on concentrated fission product solutions, began in the late 1950s in two broad areas: the containment material itself and the solidification process. After preliminary investigation of various products, notably synthetic minerals, borosilicate glass was selected because it had two major advantages: specification tolerances compatible with some variation in the component fractions to accommodate the random chemical composition of the feed solution and relative ease of industrial-scale fabrication. Moreover, although not on a par with synthetic crystals, the glass properties show good resistance to natural environmental agents. 1 fig

[en] The purpose of this document is to provide a practical summary of the Environmental Qualification Testing Program results

[en] The first industrial facility of vitrification started at Marcoule, last June. The principle of the continuous nuclear waste vitrification envisaged by France is briefly recalled together with both main functions of this vitrification: waste compaction and radioactivity confinement in time

[en] The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D₂0 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

[en] This document provides the rationale for preparing a package-specific safety document (PSSD) for the DBVS container verses developing a certified Type B package

[en] A process is described for the vitrification of wastes containing radioactive substances. A heated bed is created of particles forming glass in a reactor, a gaseous agent is used to fluidise the bed; the waste matter containing radioactive substances in the fluidised bed is sprayed so that the metals and fission products in the waste are calcinated on the particles of the substance forming the bed and the remaining part of the waste is vaporised. The particles forming glass and the calcinated wastes are then removed from the reactor

No abstract available

[en] The different methods for treatment of RAW – cementation bituminization, vitrification and immobilization in ceramic matrix, as well as the requirements for matrix materials are discussed

[en] As part of a demonstration for British Nuclear Fuels Limited, Incorporated (BNFL), the Immobilization Technology Section (ITS) of the Savannah River Technology Center (SRTC) has produced and characterized three low-activity waste (LAW) glasses from Hanford radioactive waste samples. The three LAW glasses were produced from radioactive supernate samples that had been treated by the Waste Processing Technology Section (WPTS) at SRTC to remove most of the radionuclides. These three glasses were produced by mixing the waste streams with between four and nine glass-forming chemicals in platinum/gold crucibles and heating the mixture to between 1120 and 1150 degrees C. Compositions of the resulting glass waste forms were close to the target compositions. Low concentrations of radionuclides in the LAW feed streams and, therefore, in the glass waste forms supported WPTS conclusions that pretreatment had been successful. No crystals were detected in the LAW glasses. In addition, all glass waste forms passed the leach tests that were performed. These included a 20 degrees C Product Consistency Test (PCT) and a modified version of the United States Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP)