Procedure to measure the radioactivity of radioactive...

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Reexamination Certificate

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C250S394000

Reexamination Certificate

active

06407394

ABSTRACT:

FIELD OF THE INVENTION
The present invention concerns a procedure to measure the radioactivity of radioactive material enclosed in a container, more especially to measure the radioactivity due to radioactive sources and/or active or contaminated materials set within a sealed container.
During the performance of activities in the nuclear field (power stations, research laboratories, analysis laboratories, etc.) a considerable quantity of weakly radioactive solid wastes are produced that are normally gathered in containers that are then sealed. In order to correctly manage these wastes it is necessary to be able to rapidly and reliably check the nature and extent of the contamination present.
Because we are dealing with sealed containers, the only technique applicable is that of externally measuring the &ggr; radiation, from which, by means of appropriate calculations, it is possible to achieve the overall contamination a &agr;+&bgr;+&ggr;.
The main problem in the interpretation of the results of the &ggr; measurements is the assessment of the reliability of the survey, owing to the fact that the sources are of large dimensions within which both the distribution of nature of the materials and the distribution of the activity is widely unknown.
DESCRIPTION OF THE RELATED ART
At the state of the art, the assessment of activity is generally conducted by means of the &ggr; count in various lateral positions outside the container based on the hypothesis that the contents feature a homogeneous composition and that the distribution of activity is known, or else by means of the &ggr; dose measurement performed along the sides of the container, measurements from which one then finds the value of the source activity by means of appropriate calculation procedures.
Document JP 60 076680 A is known that discloses a surface dose rate measuring apparatus wherein a drum-shaped object to be measured is rotated and moved up-and-down so as to be opposed to two surface dose rate detectors, each provided with a shielding element that shields radiations from the undesired directions and moved in relative relation to the other one, the maximum radiation value being efficiently determined at time of scanning due to the detectors relative movement.
SUMMARY OF THE INVENTION
Laboratory measurements conducted on containers originating from nuclear power stations, some of which contained exhausted ion exchange resins and others with technological wastes, have shown differences also in excess of twice the values of activity calculated with such techniques and those of the true activity, as a consequence, the criteria for radiation protection adopted in the handling and storage of low specific activity wastes appear to be excessively conservative.
The invention obviates the above-mentioned drawbacks; it is a procedure to measure the radioactivity of radioactive materials enclosed in a container by means of &ggr; ray detectors positioned laterally, outside the container and, comprises the following phases of:
i) weighing a known volume container in order to determine the average density of its content;
ii) positioning the container upon a support;
iii) positioning on respective supports two &ggr; ray detectors set symmetrically compared to a main transversal axis of the container, facing the smaller walls of the container;
iv) vertically moving the container, so that its main longitudinal axis coincides with the axis connecting the two detectors;
v) moving the two detectors upon their respective supports in order to stop them in a sampling position, along said longitudinal axis, symmetrical with the container where the intensity of the radiation from the container is sampled in order to define the counting geometry;
vi) moving the two detectors upon their respective supports in order to stop them in a counting position symmetrical compared to the container, that proves to by suited to providing measurements of the radiations that are an optimum in terms of accuracy of the measurements and measurement time, the distance of such positions generally being greater than the largest dimensions of the walls of the container facing the detectors;
vii) measuring the &ggr; radiation and calculating the geometric mean (C1-C2)
½
, expressed as cps (counts per second), of the counting ratios (C1,C2) of the two detectors, such a geometric mean being linked to the intensity I of the corresponding &ggr; radiation by the following formula
 (C1·C2)
½
=I·&bgr;·F1·F2·(&agr;/D
2
)·exp(−&mgr;*·L/2)  (1)
when the activity is mainly concentrated in a limited area of the container, and alternatively by the formula
(C1·C2)
½
=I·&bgr;·F1·F2·(&agr;/D
2
)·(1−exp(−&mgr;*·L))/(&mgr;*·L)  (2)
when the activity is distributed in a sensibly uniform manner within the container;
viii) calculating the intensity I of the &ggr; radiation by means of one of the above formulae.
It is understood that the container, generally in the form of a cylindrical drum, will be preferably positioned with its longitudinal axis horizontal so that each of the two circular walls faces one of the detectors. It is also understood that the positioning of the two detectors symmetrically compared to the main transversal axis of the container is not a compulsory condition; a non-symmetricall positioning only involves a greater complexity of the mathematical procedure.
In the above formulae: &mgr;*=(2/D)+&mgr;
where
&mgr; is the mean attenuation coefficient for the material contained, expressed as cm

,
I is the radiation intensity of the source, expressed as dps (disintegrations per seconds, or Bq),
&bgr; is the branching of the &ggr; line considered,
F1 is the absorption factor of the container base,
F2 is the absorption factor in air,
&agr; is a parameter expressed in cm
−2
that depends on the energy of the photons and on the characteristics of the detectors, but not on the distance between container and detector, nor on the dimensins of the container, or on the nature of the wastes; &agr; is calculated from the values of C
(D1)
and C
(D2)
shown below,
D is the distance between a detector and the wall of the container facing the detector, expressed in cm, including the distance covered on average by the photons inside the container (in practice D is the distance between said wall of the container and the cetre of the detector),
L is the height of the container, expressed in cm.
The quantities &bgr;, D, L are known, while F2, very cose to 1, is calculated. The calibration of the apparatus hence requires the determining of &agr; and F1 versus the energy.
To this purpose a series of measurements are performed by using one detector only and setting calibrated sources, grouped in various ways, outside an empty container, as close as possible to its walls opposite the detector, both walls being on one side of the detector and on the other (distances D1 and D2, are shown in FIG.
2
).
At a given energy of the calibrated sources the counting ratios in cps in the two positions, one at a distance D1 and the other at a distance D2 from the detector, are expressed as:
C
(D1)
=I·&bgr;F2
(D1)
·&agr;/D1
2
C
(D2)
=I·&bgr;·F1
2
·F2
(D2)
·&agr;/D2
2
where
F2
(D1)
and F2
(D2)
are the absorption factors in the air at the distances D1 and D2 from the detector, respectively.
The quantity F1 is obtained by:
F1=((C
(D2)
·D
2
2
·F2
(D1)
)/(C
(D1)
·D1
2
·F2
(D2)
))
½
,
and &agr; is obtained by
&agr;=(C
(D1)
·D1
2
)/(I·&bgr;F2
(D1)
).
Because the chemical composition of the wastes is not known, also the value of the attenuation coefficient at a given energy required to calculate efficiency is not known.
However, within the energy interval involved in this type of measurement the attenuation coefficient at a given energy, expressed in cm
2
/g, is sensibly independent from the atomic number. This leads to the ratio between attenuation coefficients of the two different substances, expressed in cm
−1
, is roughly equal to the ratio between the

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