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QUICK MEASURING METHODS OF RADIONUCLIDES IN MATERIALS AND WASTES DURING DECOMMISSIONING OF NUCLEAR INSTALLATIONS

Objective

Under the ALARA guidelines of the German Radiological Protection Ordinance, it is necessary to know the exact amount of radioactivity and the radiological potential of the materials of installations to be decommissioned.

The objective of this work programme is to determine a correlation between the gamma and beta emitters (electron capture nuclides) by analysing the activation products and contaminants in reactor materials and in waste products. These informations are essential for determining the radioactivity released to the environment and for radiological protection of the public and the personnel.

The extracted material (eg, iron) will be submitted to beta-activity measurements, followed by a gamma-activity determination. The correlation of both measuring methods should make it possible to reduce the determination of the total radioactive material quantity to gamma-spectroscopic analyses.

The work programme will be performed in contact with the Chemistry Division, Harwell Laboratory UKAEA, especially concerning the exchange of measuring methods.
The objective of this work programme is to determine a correlation between the gamma and beta emitters (electron capture nuclides) by analysing the activation products and contaminants in reactor materials and in waste products. This information is essential for determining the radioactivity released to the environment and for radiological protection of the public and the personnel. The extracted material (eg iron) will be submitted to beta activity measurements, followed by a gamma activity determination. The correlation of both measuring methods should make it possible to reduce the determination of the total radioactive material quantity to gamma spectroscopic analysis.

After calibration of the coaxial germanium detector and low level proportional counter specially for concrete and steel samples, the determination of the activity of these samples took place. The measured samples (steel and concrete) were processed chemically and their content of iron was determined. The samples are being processed for liquid scintillation counting to determine the contribution of beta activity of iron-55.
WORK PROGRAMME

1. Acquisition of instrumentation (TUV-SWD)

2. Choice and procurement of representative samples from the reactors MZFR, FR2, KNK and/or KWO (TUV-SWD)

3. Laboratory activities, reference measurements and correlation calculations for nuclear determinations on decommissioning wastes (all)

4. Evaluation and documentation of the results (TUV-SWD)

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

Technischer Überwachungsverein Südwestdeutschland eV
Address
Dudenstraße 28
68167 Mannheim
Germany

Participants (1)

Fachhochschule Gießen-Friedberg
Germany
Address
Wiesenstraße 14
35390 Giessen