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<strong>atw</strong> Vol. 64 (<strong>2019</strong>) | Issue 3 ı March<br />

measurement time for the individual<br />

segment. This results in an average<br />

over the ­angular profile for each segment,<br />

where the ratio of true to assumed<br />

­efficiency at a gamma energy<br />

of 1408 keV is reduced to maximally<br />

3.3 and therefore the activity of this<br />

segment would be overestimated by<br />

this factor. At this gamma energy, the<br />

summation over all 10 segments<br />

­results in a ratio of 0.95, which means<br />

that SGS reaches the true value of<br />

the activity. This, however, is pure<br />

coincidence and depends on the<br />

gamma energy of the line used for<br />

evaluation and the density of the<br />

matrix: at the gamma energies of 122,<br />

344, 779, 964, 1112 keV the ratio of<br />

reconstructed to true activity for SGS<br />

amounts 0.09, 0.32, 0.66, 0.75, 0.82,<br />

respectively.<br />

To evaluate the ASGS method, a<br />

MCNP model of the 78 MBq Eu-152<br />

activity distribution and the waste<br />

drum was implemented, where full<br />

gamma spectra for the 40 % n-type<br />

detector were simulated for every<br />

measurement position (Figure 8). A<br />

full sectorial scan for three segments<br />

and 12 sectors per layer was simulated<br />

with in total 36 measurement positions,<br />

where the measurement time<br />

for each position is 120 seconds. For<br />

the ASGS geometry, the collimator<br />

design is such that it covers a larger<br />

area of the drum surface in the vertical<br />

direction and therefore less vertical<br />

scan positions are needed (see Figure<br />

6 bottom-right). The spectra were<br />

analyzed using a gamma spectrum<br />

analysis software and the peak area<br />

was evaluated for six Eu-152 gamma<br />

lines at 122, 344, 779, 964, 1112, and<br />

1408 keV. The peak efficiencies were<br />

calculated for different source partition<br />

models using the ECIAD tool<br />

which were used as an input for the<br />

reconstruction using the non-negative<br />

least squares reconstruction algorithm.<br />

Using the analysis of two of the<br />

in total six gamma lines of Eu-152, the<br />

reconstruction algorithm can assign<br />

the activity to the correct location in<br />

the partitioned model and the total<br />

activity is reconstructed to 77.1 MBq<br />

(using the 1112 and 1408 keV lines),<br />

which is an underestimation of 1.3 %<br />

of the true activity. The result for the<br />

reconstructed activity did not vary<br />

strongly with the choice of gamma<br />

lines used and the deviation ranges<br />

from -1.3 % to +4.7 % of the true<br />

activity. The reconstruction algorithm<br />

leads to a solution, where a small part<br />

of the activity is assigned to the neighboring<br />

layers of the source partitions,<br />

however, this is only a minor effect<br />

| | Fig. 8.<br />

Simulated spectra for sectorial scanning of the simulated test case containing a localized Eu-152 activity distribution.<br />

and is attributed to the noise in the<br />

gamma spectrum. This showcase<br />

demonstrates, that the partitioned<br />

source model can reconstruct a<br />

non-uniform activity distribution.<br />

Uncertainties, decision<br />

threshold and detection limit<br />

For gamma scanning the largest<br />

uncertainty contribution stems from<br />

the unknown location of the uncertainty<br />

which is attributed as ‘model<br />

uncertainty’. These errors are evaluated<br />

by assuming worst-case scenarios<br />

for a non-homogeneous activity distribution<br />

and are treated as Type B<br />

­uncertainties according to the GUM<br />

and DIN ISO 11929. For the cement<br />

waste matrix used in the previously<br />

mentioned test case, single point<br />

sources located in various positions of<br />

the waste drum were simulated and<br />

evaluated with SGS and the ASGS<br />

reconstruction method. In ASGS a<br />

­finer radial subdivision was chosen<br />

with 6 radially subdivided partitions<br />

for each 30° sector. Hereby, an improved<br />

spatial resolution can be<br />

reached to reconstruct a localized<br />

activity distribution. With ASGS the<br />

reconstruction method localizes the<br />

point source and therefore this<br />

information reduces the ‘model uncertainty’<br />

relative to SGS. For ASGS<br />

the reconstruction is made for the<br />

evaluation of several combinations of<br />

two gamma lines of Eu-152. Even<br />

though the linear system of equations<br />

is underdetermined the reconstruction<br />

algorithm was able to solve the<br />

minimization problem. A comparison<br />

of the ratio for A reco/A true<br />

is shown for<br />

four different point source locations<br />

(indicated as green dots in Figure 6)<br />

representing locations where the<br />

radiation from the source experiences<br />

maximal and minimal self-attenuation<br />

within the active matrix (Table 1<br />

– Ratios of true to reconstructed<br />

activities for simulated point source<br />

activities located at four different<br />

positions within the waste drum for<br />

SGS and ASGS.). In SGS this ratio<br />

strongly depends on the gamma line<br />

chosen for evaluation and for the<br />

worst case for the gamma line at<br />

122 keV the activity is underestimated<br />

up to a factor of 50 and overestimated<br />

by a factor of 4. In ASGS multiple lines<br />

are used in the analysis, where<br />

the reconstruction of the simulated<br />

measurement of point source activity<br />

was performed using two lines, three<br />

lines, and six lines. For the line energy<br />

combinations shown in Table 1 the<br />

largest spread is observed when the<br />

122 and 1408 keV lines is chosen for<br />

the reconstruction with an underestimation<br />

by a factor of approximately<br />

1.2 and an overestimation<br />

by a factor of approximately 1.8. This<br />

spread represents also the worst case<br />

in ASGS for all line combinations of<br />

the six strongest Eu-152 lines. Therefore,<br />

ASGS reconstruction reduces the<br />

bandwidth of errors which is potentially<br />

caused by the unknown activity<br />

distribution and therefore this lack<br />

of information leads to lower model<br />

uncertainties and correspondingly<br />

much lower conservative estimates<br />

than in SGS.<br />

The ASGS system relies on the<br />

spatial reconstruction of the activity<br />

and therefore uses the spatial information<br />

of the gamma count rate recorded<br />

at the different measurement<br />

positions of the waste drum. The decision<br />

threshold determines the minimum<br />

amount of the radionuclide<br />

DECOMMISSIONING AND WASTE MANAGEMENT 165<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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