INDUSTRIAL-SCALE MELTING OF TRITIUM-CONTAINING STEEL FROM NUCLEAR INSTALLATIONS

Project Information

Grant agreement ID: FI2D0014

Project closed

Start date 1 July 1990

End date 1 May 1993

Funded under

• Specific research and technological development programme (Euratom) in the field of decommissioning of nuclear installations, 1989-1993

Total cost € 474 000,00

EU contribution € 237 000,00

Coordinated by

SIEMPELKAMP NUKLEAR- UND UMWELTTECHNIK GMBH & CO.
Germany

Objective

The objective and scope is to subject steel scrap, coming from decommissioning, to (among others) a special tritium removal treatment in order to reduce the amount of waste which has to be disposed.

The proposed work consists in trapping the tritium released from scrap during the heating and melting process in a specially adapted exhaust system of the melting facility. For this project the already existing facility has to be modified, adapted and tested. The estimated steel quantities for the treatment amount to circa 18 Mg with exhaust gas streams of about 5,000 m cubic/h.
The objective and scope is to subject steel scrap, coming from decommissioning, to a special tritium removal treatment in order to reduce the amount of waste which has to be disposed. The proposed work consists in trapping the tritium released from scrap during the heating and melting process in a specially adapted exhaust system of the melting facility.

A representative charge of tritium containing material was found at nuclear power plants and at a tritium laboratory. The waste consists of 13 tritium gas bottles and more than 1000 kg of dismantled tubes, valves and housing materials. Due to the fact that uncertainties occur with respect to the degree of activity, samples were sent to the Nuclear Resarch Centre Juelich, in order to determine the level of activity. A test plan for measurement techniques was elaborated and the tritium elimination device was chosen.
WORK PROGRAMME

1. Material choice: Laboratory evaluations on samples coming from parts of the NPP Niederaichbach will provide a representative charge of material. (all)

2. Radiological measurements: which consists in choosing the tritium elimination device in accordance with the measurement techniques. (all)

3. Modification of the existing plant with integration of the new components. (SG)

4. Determination of tritium release during heating up at different temperature steps. (SG)

5. Evaluation of the released tritium activity. (all)

6. Documentation of the collected results. (all)

Fields of science (EuroSciVoc)

CORDIS classifies projects with EuroSciVoc, a multilingual taxonomy of fields of science, through a semi-automatic process based on NLP techniques. See: https://op.europa.eu/en/web/eu-vocabularies/euroscivoc.

• engineering and technology › other engineering and technologies › nuclear engineering

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Programme(s)

• FP2-DECOM 3C - Specific research and technological development programme (Euratom) in the field of decommissioning of nuclear installations, 1989-1993

Topic(s)

• A4 - Treatment of specific waste materials

Call for proposal

Data not available

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

SIEMPELKAMP NUKLEAR- UND UMWELTTECHNIK GMBH & CO.

• EU contribution: No data
• Address: 45,Siempelkampstra?e 45 ; 47803 Krefeld ; Germany
• Total cost: No data

Participants (1)

NIS INGENIEURGESELLSCHAFT MBH

Germany

• EU contribution: No data
• Address: 23,Donaustrasse 23 ; 63452 HANAU
• Total cost: No data