A new system has been designed to automatically load the samples to be irradiated at the gamma irradiation facility of the Nuclear Technology Development Centre (CDTN) at Belo Horizonte, Brazil. The objective of this system is the optimization of the experiments performed at the Gamma Irradiation Laboratory for short-time irradiations without interruption of the irradiator cycles. The installation of this new system requires the opening of a hole at the labyrinth door to allow the loading of irradiating products. Due to this alteration on the original design, the door opening into the labyrinth requires shielding verification. The dose rate with the door open is calculated using Monte Carlo MCNPX v 2.6.0 code. The Monte Carlo source simulations were validated with experimental measurements of dose rate. The simulation demonstrated that a hole can be opened at the labyrinth entrance when installing an automatic loading system. Not only does it comply with dose constraint requirements, but it also complies with national and international standards.
Gamma Irradiation Laboratory installed at the Nuclear Technology Development Centre (CDTN), Belo Horizonte, Brazil, has shown a wide range of applications. To date, this irradiator has been used for a number of applications like inactivation of pathogenic microbes in infected blood products, preventing graft-versus-host disease (GVHD) in immune suppressed patients [
The high demand of the gamma irradiation facility to conduct the wide range of applications, as previously mentioned, requires innovative solutions that could bring improved gamma irradiation facility efficiency. A new automatic product loading system for the laboratory was proposed [
As a result, the idea of installation and operation of this system requires the opening of a hole at the labyrinth door to allow the loading of irradiating products without interrupting irradiator operation. One of the requirements for installation was a premise that followed from the conceptual design: the installation must not compromise personnel safety or equipment operations. Due to this alteration of the original design, we needed to know the gamma doses rates and profile that resulted from opening the door of the labyrinth.
International Commission on Radiological Protection (ICRP) recommends the cumulative dose limit of 20 mSv/y averaged over five years for occupational exposed workers and 1 mSv/y for the public [
The objective of this study is to verify, using Monte Carlo MCNPX v 2.6.0 code [
The 60Co gamma rays source of the gamma irradiation facility has maximum activity of 2.220 TBq (60.000 Ci), which is composed by 12 double encapsulated radioactive pencils placed in a rack. The facility is classified by the IAEA as category II (dry storage facility) and source category based on the activity thresholds for radionuclides is classified as category 1 [
The labyrinth was modelled with the Monte Carlo code MCNPX v. 2.6.0. This model includes geometric and structural details of the source of the irradiator and the labyrinth with walls, ceiling, floor, and door. The concrete of walls, floor, and ceiling was assumed to have a density of 2.453 g/cm3 (being heavier than ordinary concrete) and to have the elemental compositions of ordinary concrete. The ordinary concrete composition in weight fraction was H (0.0221), C (0.0024), O (0.5749), Na (0.0152), Mg (0.0012), Al (0.0199), Si (0.3046), K (0.0100), and Ca (0.042). The composition of the concrete was taken from the International Commission on Radiation Units and Measurements [
The MCNP option utilized for this problem was the energy fluence (tally Mnemonic
MCNP Dose energy card (DEn) and Dose function card (DFn) were used to introduce the conversion factors from energy fluence into the kerma in air. These factors are the
MCNPX was run in photon and electron mode (mode PE) to pick up bremsstrahlung photons. The photon and electron physics are controlled with two cards (PHYS:P and PHYS:E). A detailed photon physics treatment, including photoelectric effect with fluorescence production, incoherent and coherent scattering, and pair production, has been considered in the energy range between 0.001 and 2.6 MeV with “PHYS:P” card. For electron transport, MCNP addresses the sampling of bremsstrahlung photons at each electron substep. The “PHYS:E” card is utilized in MCNP for biasing some physical parameters such as production of secondary electrons by photons, coherent scattering, bremsstrahlung angular distribution, and production of characteristic X-rays.
In order to accelerate the calculations, the MCNP code has been parallelized in Intel’s Core i7 CPU with 3.4 GHz and 8 GB RAM, using the MPI multiprocessing parallel protocol, in this case with 8 processors. This way, the problem speedup is achieved. It was taking into consideration the worst situation regarding maximum dose rate: the door has the full opening hole in the labyrinth entrance with any additional shielding.
Figure
Diagram of the new automatic product loading system for the Gamma Irradiation Laboratory with the opening door of labyrinth.
The dose rate assessments were performed for 9 points of interest inside the labyrinth of the irradiator (with concrete walls of 1.9 m) and 1 point at the labyrinth entrance. Figures
MCNPX model
MCNPX model
The detailed MCNPX shielding source container used for transport and storage of the GB-127 cobalt-60 source is presented in the previous work [
In order to obtain a statistical error lower than 5%, about 50 × 106 photon stories were calculated. The CPU processing time was approximately 5 days with MPI multiprocessing parallel protocol with 8 processors. In order to reduce the variance and speed up the calculations, the cell importance technique was employed. The generated cell importance rises with increasing distance from source to detector. The cell importance will be highest closer to detector. It is keeping the ratio of adjacent importance small (2 or less than 4) to avoid unnecessary creating too many particles. The cell importance took the values from 1 (source), 2, 4, 8, 16, 32, 64, and 128 to 256 (at point of interest). A value of 0 was assigned to the area outside of rectangular parallelepiped surface. Instead of the sphere as exclusion surface, rectangular parallelepiped surface is used to allow reducing the computation time. The points tallied along the passage of the labyrinth are illustrated in Figure
MCNPX model
The isodose curves in % of the gamma dose rate distribution using MATLAB in the GB-127 source are presented in Figure
MCPX model and isodose curves in % representation of XY view of the gamma dose rate distribution in the GB-127 source.
It can be observed from this figure that sources rack consists of 24 holes with 12 double encapsulated radioactive cylindrical pencils, model C-198. The total initial activity of the sources was 2.127 TBq (57.494 Ci) (18 August 2011).
Figure
Dose rate distribution as function of positions of evaluated points obtained with MCNPX code with
The radiation doses detected at points 4 and 5 are the result of secondary gammas produced by Compton scattering and by production of pairs, which are scattered and transmitted in the lower left corner of the labyrinth. There is a rapid reduction between points 4 and 5 and although point 5 is closer to the primary source, fewer dispersion gammas arrive from the lower left corner. That makes the radiation in the corridor, where points 1, 2, 3, 4, and 5 are located, higher than that in the corridor with points 6 and 7, and, in turn, the radiation here is much lower than that in the corridor where points 8 and 9 are located. There is a reduction between 5 and 6, given that the scattered gammas do not reach the bottom wall even though that wall is closer to the primary source.
It is observed that the dose rates are decreasing considerably along the corridor in the direction of the labyrinth door, as expected. At position 1, the dose rate is very high, since this point receives the primary gamma radiation beam from the cobalt source. At the other positions, the incident radiation beam is originated from the secondary reflections or transmission on the shielding walls.
The knowledge of the doses inside the labyrinth (points 1 to 9) is relevant in terms of doses deposited in the product in order to be able to implement a protocol of irradiation for some products. These doses are not important in terms of radiation protection in the sense that no one can be in these zones. Only point 10 (outside the door) is important in terms of radiation protection.
From the simulated results, it was observed that dose rates at point 10 were not significantly changed when considering the original project and the proposed modification with inclusion of the hole at the labyrinth door to allow the loading of irradiating products.
Table
Comparison of dose rate without and with hole at the labyrinth entrance door obtained with MCNPX code with
Position | Without hole |
With hole |
---|---|---|
9 | 0.40 | 0.90 |
10 | 1.40 | 1.80 |
It is worth mentioning that even in this worst-case scenario (hole at the labyrinth entrance door) calculations show that at all point of interests evaluated the doses rates are well below the occupational limit of 3
The dose rate at position 10 is slightly higher than that of position 9 (inside the door). The value was calculated by
Therefore, even though the relative error with F5 tally was lower than 5%, as mentioned earlier, this may be a false result, because the gamma dose rate outside the door (at position 10) ought to be lower than the dose rate inside the door (at position 9) by the gamma attenuation.
In the future work the radiation buildup with the code MCNPX will be calculated and compared with the one obtained by conventional methods. It is necessary to make 2 calculations with the code MCNPX: one with all the structural materials of the system and another with only the primary beam of the source without the structural components of the system (labyrinth structures and walls). In the source definition, we will use a homogenized cylindrical model [
TLD dosimeters were used for validation of calculated gamma doses. In 2014, the sources rack consists of 24 holes with 16 double encapsulated radioactive cylindrical pencils and the source activity was 1,427 TBq (38.585 Ci). Table
Comparison between measured and calculated gamma doses rates at position 10.
Position | MCNPX D ( |
Measured |
% difference |
---|---|---|---|
10 | 3.40 | 2.80 | 21 |
The simulations have overestimated experimental dose rate values with a difference of 21% and 1.9%, compared with the experimental data. The gamma dose rate after the door will not exceed the limit established by the standards for OEIs in controlled area, namely, 3
To validate the simulation, we have the doses rates measured by MDS Nordion-supplied Fricke dosimeters at a distance of 1 m from the source centre, near each of the turntables on 30 August 2002 [
Table
Comparison between the values of the doses rates at a distance of 1 m from the source centre for each position obtained from simulation and reference values.
Position | MDS Nordion-supplied Fricke absorbed-dose rate (Gy/h) | MCNPX |
% error |
---|---|---|---|
1 | 543.00 | 586.63 |
|
2 | 556.00 | 589.61 |
|
3 | 546.00 | 575.64 |
|
4 | 556.00 | 573.40 |
|
As shown
A numerical model of the labyrinth of the gamma irradiator was implemented for the first time. In addition, any future changes in the geometry and the shielding of the facility can be calculated beforehand and optimized as well. This simulation could become an alternative to experimental dosimetry measurements.
The Monte Carlo code MCNP was used to verify the shielding at the labyrinth entrance door, even with the hole at the labyrinth entrance door opened (worst-case scenario). The obtained dose rate value is below the established dose limits by the national Brazilian regulations and the international recommendations for workers in controlled areas of 3
The authors declare that they have no conflicts of interest.
This work was supported by the following Brazilian institutions: Nuclear Technology Development Centre (CDTN), Brazilian Nuclear Energy Commission (Cnen), Research Support Foundation of the State of Minas Gerais (Fapemig), Brazilian Council for Scientific and Technological Development (CNPq), and Coordination for the Improvement of Higher Education Personnel (Capes).