Gateway for:

Member Countries

Vitrificated Nuclear Waste


Verification of the New Model of Leaching of Vitrificated Nuclear Waste Using a Single Pass Flow-Through Test Method – Participation in the International Program

Tech Area / Field

  • ENV-RWT/Radioactive Waste Treatment/Environment
  • ENV-WDS/Waste Disposal/Environment

3 Approved without Funding

Registration date

Leading Institute
Khlopin Radium Institute, Russia, St Petersburg


  • Lawrence Livermore National Laboratory, USA, CA, Livermore\nArgonne National Laboratory (ANL) / Chemical Engineering Division, USA, IL, Argonne

Project summary

The main objectives of the project are:

- Construction of the apparatus equipped with test instrumentation; preparation and fulfillment of the scientific program to study the behaviour of nuclear waste glasses in groundwater environment using the single pass flow-through test method.

- Presentation of the results in the format of the international program to evaluate the precision and bias with which the forward dissolution rate of a specified borosilicate glass can be measured using a single-pass flow-through test method.

The predictions of glass matrices behavior in different disposal systems based on the currently existing methods and databases are not reliable. A major problem is the construction of a correct mathematical dynamic model of glass dissolution process verified by the results of the single path flow-through glass dissolution rate measurements.

Glass dissolution rate is a key parameter used in the prediction of specified glass wastes degradation, radionuclides release into environment and in designing the engineered barriers of radioactive waste disposal systems.

Experimental study of vitrified waste behavior in geological formations is a labor and resource intensive task and the methodology of such study (as far as we know) has not been developed even for laboratory scale experiments.

At the V.G. Khlopin Radium institute the theory of glass dissolution process is being developed and experimental data are being obtained and accumulated necessary for glass waste dissolution parameters determination and prediction at test conditions close to the real waste storage and disposal situations. The work places for conducting measurements and data analysis have been prepared and preliminary investigations of waste glass behaviour in dynamic mode of leaching conducted. The results confirmed the validity of the method based on the measurement of the forward dissolution rate of matrices incorporating radioactive waste in regimes simulating natural conditions met at disposal sites.

The significance of the problem is realized all over the world. The Argonne National Laboratory (USA) has proposed to conduct a joint bench-mark experiment with the objective to develop at the international scale the most acceptable and promising method of assessment the solidificated waste suitability for disposal and obtain a set of interconnected characteristics of the process.

The program is appreciated by a number of foreign institutes and organizations. The following organizations and scientists are expected to participate in the study:

SNL: Brady Pat; LLNL: Bourcier Bill; PNNL: Hanson Brady, McGrail Pete, Smith Gary; ANL: Jeong Seung-Young, ANL-W: Johnson Steve; Southwest Research Institute: Jain Vijay; SRTC: Jantzen Carol; Karlsruhe, Germany: Kienzler Bernhard; CEA, France: Latge Christian, Veyer Catherine; SRTC: Lorier Troy; JNC, Japan: Mitsui Seiichiro; CUA-VSL: Pegg Ian; SCKCEN, Belgium: Van Iseghem Pierre.

V.G. Khlopin Radium institute has been invited to participate in an interlaboratory study - testing program to evaluate the precision with which the dissolution rate of borosilicate waste glass can be measured.

The ISTC project proposal includes the following stages:

- Completion of the theoretical process model development and development of the corresponding measurement technique;

- Conduction of verification experiments and computer analysis of the data obtained;

- Fulfillment of the Program of the Interlaboratory Study to evaluate the precision of borosilicate glass dissolution rate measurement using a single-pass flow-through (SPFT) test method;

- Analysis of the experimental data and presentation the results in the International Project format;

- Integration the results obtained into the US radioactive waste management program with the objective to develop a new US standard practice for radioactive waste glass testing.

An updating of the instrumentation is provided by the project plan to bring the quality of the experiments to the contemporary level.

If this project is supported, Radium Institute will take an active part in the international collaboration and undoubtedly contribute to solving the problem of global significance – nuclear waste disposal.


The International Science and Technology Center (ISTC) is an intergovernmental organization connecting scientists from Kazakhstan, Armenia, Tajikistan, Kyrgyzstan, and Georgia with their peers and research organizations in the EU, Japan, Republic of Korea, Norway and the United States.


ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.

Promotional Material

Значимы проект

See ISTC's new Promotional video view