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<strong>atw</strong> Vol. 64 (<strong>2019</strong>) | Issue 3 ı March<br />
DECOMMISSIONING AND WASTE MANAGEMENT 166<br />
E [keV] Center Drum wall<br />
activity for a given gamma line which<br />
can be detected with a high degree of<br />
certainty in the gamma scan. In ASGS,<br />
the evaluation of the decision threshold<br />
and the detection limit is performed<br />
based on the individual spectra<br />
and not on the averaged gamma<br />
spectrum as in conventional SGS.<br />
When a ‘hot spot’ of localized activity<br />
is present in the drum, the evaluation<br />
of the characteristic limits applied in<br />
SGS then becomes invalid whereas<br />
the variation in the count rate in<br />
different measurement positions is<br />
accounted for in the ASGS analysis of<br />
the measurement data. In terms of<br />
increasing the detection efficiency,<br />
ASGS uses a larger aperture than the<br />
typical collimator geometry used for<br />
SGS which results in a photopeak<br />
efficiency which is by a factor 50<br />
higher. Assuming the background<br />
emanates from the activity within the<br />
waste drum to be measured, the decision<br />
threshold for detection of radionuclides<br />
scales with the square root of<br />
the efficiency, such that a significant<br />
reduction by an order of magnitude<br />
can be reached for the ASGS system as<br />
compared to the SGS method within<br />
the same time for the measurement.<br />
Summary<br />
ASGS offers a measurement method<br />
for characterization of radioactive<br />
waste which significantly reduces the<br />
model uncertainty based on a spatially<br />
resolved reconstruction. The<br />
ASGS software is designed to permit<br />
the automated operation of the<br />
gamma scanning system which<br />
includes the analysis of the data. The<br />
dedicated ECIAD software module is<br />
developed for the calculation of<br />
Bottom Middle Bottom Middle<br />
SGS 122 0.02 0.04 2.76 4.08<br />
344 0.19 0.37 1.78 2.40<br />
779 0.59 1.13 1.26 1.99<br />
964 0.70 1.33 1.09 1.72<br />
1112 0.78 1.50 0.98 1.63<br />
1408 0.97 1.89 0.92 1.52<br />
ASGS 122 - 1408 0.82 0.99 1.56 1.79<br />
344 - 1408 0.85 1.<strong>03</strong> 1.16 1.41<br />
779 - 1408 0.83 1.01 1.02 1.27<br />
964 - 1408 0.80 0.97 1.01 1.25<br />
1112 - 1408 0.79 0.95 1.00 1.25<br />
122 - 779 - 1408 0.78 1.37 1.02 1.60<br />
all Lines 0.81 1.17 1.01 1.38<br />
| | Tab. 1.<br />
Ratios of true to reconstructed activities for simulated point source activities located at four different<br />
positions within the waste drum for SGS and ASGS.<br />
mathematical efficiencies for a partitioned<br />
source model, the reconstruction<br />
of spatially resolved activities,<br />
and the uncertainty calculation. The<br />
ECIAD software operates without<br />
user guidance in an automated fashion<br />
using a priori information on the<br />
waste drum. With a suitable interface,<br />
this information can be retrieved by<br />
the software prior to the analysis from<br />
a database. As a result, lower conservative<br />
estimate can be reached<br />
than in conventional gamma scanning<br />
systems, since the spatial information<br />
on the activity distribution is used for<br />
the evaluation of the measurement<br />
data. Therefore, ASGS provides a far<br />
more accurate characterization of the<br />
true activity which facilitates a better<br />
use of the allowed activity limits. With<br />
ASGS, the evaluation is performed<br />
in a consistent manner and will be<br />
coupled with the calculation of uncertainties<br />
according to the current<br />
norms and guidelines for the evaluation<br />
of uncertainties. The evaluation<br />
model for the activity is based on a<br />
reconstruction algorithm which precludes<br />
the propagation of uncertainties<br />
using the general law of error<br />
propagation. Therefore, the propagation<br />
of uncertainties is calculated<br />
using Monte-Carlo based methods for<br />
the determination of characteristic<br />
limits according to the requirements<br />
of the current guidelines. An experimental<br />
validation of the measurement<br />
method for various measurement<br />
configurations for the active matrix<br />
compositions and density and for<br />
different activity distributions is<br />
planned for the near future using the<br />
newly designed gamma scanning<br />
system.<br />
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Authors<br />
M. Dürr<br />
K. Krycki<br />
B. Hansmann<br />
T. Hansmann<br />
A. Havenith<br />
Aachen Institute for Nuclear<br />
Training GmbH<br />
M. Fritzsche<br />
D. Pasler<br />
T. Hartmann<br />
Mirion Technologies (Canberra)<br />
GmbH<br />
Decommissioning and Waste Management<br />
Advanced Sectorial Gamma Scanning for the Radiological Characterization of Radioactive Waste Packages ı M. Dürr, M. Fritzsche, K. Krycki, B. Hansmann, T. Hansmann, A. Havenith, D. Pasler and T. Hartmann