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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 />

References<br />

[1] VGB PowerTech e.V., Waste disposal for nuclear power<br />

plants, Essen, Germany: Working Panel Waste<br />

Management, VGB PowerTech e.V., 2012.<br />

[2] International Atomic Energy Agency, Disposal of Radioactive<br />

Waste – Specific Safety Requirements, IAEA Safety<br />

Standards Series No. SSR-5, International Atomic Energy<br />

Agency, Vienna, 2011.<br />

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Nuclear Power Estimates for the Period up to 2050, Vienna,<br />

Austria: International Atomic Energy Agency, 2018.<br />

[4] P. Brennecke, Requirements on Radioactive Waste for<br />

Disposal (Waste Acceptance Requirements as of December<br />

2014) – Konrad Repository, BfS – Federal Office for<br />

Radiation Protection, Salzgitter, 2015.<br />

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[7] ISO, Determination of the characteristic limits (decision<br />

threshold, detection limit and limits of the confidence<br />

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activity content in homogeneous radioactive waste<br />

drums, Nuclear Instruments and Methods in Physics Research<br />

A, vol. 701, pp. 262-267, 2013.<br />

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and Nuclear Chemistry, vol. 264, p. 213, 2005.<br />

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and R. Venkataraman, The efficiency calilbration of<br />

non-destructive gamma assay systems using semi-analytical<br />

mathematical approaches, in Proceedings of the WM2010<br />

Conference, Phoenix, AZ, 2010.<br />

[15] T. Bücherl, Synopsis of Gamma Scanning Systems, European<br />

Commision, Garching, 1998.<br />

[16] R. Venkataraman, S. Croft, M. Villani, R. D. McElroy und<br />

R. J. Estep, Total Measurement Uncertainty Estimation for<br />

Tomographic Gamma Scanner, in Proceedings of 46 th<br />

Annual INMM Meeting, Phoenix, AZ, 2005.<br />

[17] R. Venkataraman, F. Bronson, V. Abashkevich, B. M. Young<br />

und M. Field, Validation of in situ object counting system<br />

(ISOCS) mathematical efficiency calibration software, Nuclear<br />

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pp. 450-454, 1999.<br />

[18] T. Goorley, MCNP6.1.1-Beta Release Notes, Los Alamos<br />

National Laboratory, Los Alamos, 2014.<br />

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

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