In present simulations, we have used the BO-2014 GCR model for the 2010 solar minimum GCR event, the GCR was expected to occur at 1 AU in free space for all analyses. Fraction of dose equivalent, LET, and Flux are simulated for aromatic materials in mSv/year at various thicknesses using HZETRN 2015 (Slaba 2013; Slaba et al. 2013, 2015; Norman et al. 2013; Wilson et al. 2014, 2015b, 2015a).
The maximum energy loss from charged particles transfer to the target material and being accumulated during interactions between ions and shielding. The accumulated energy in shielding is calculated using linear energy transfer (LET),
Where dE is energy accumulated in the target material, and dx is the length of the path travelled by the particle in the material.
Materials
In this analysis, we consider three High Hydrogen containing aromatic materials namely Polyetherimide, Polysulfone, and Polyimide. The selection of these shielding materials are based on their high amount of hydrogen atoms and low density. The ultimate goal is to make a light weight and effective shield and therefore material should have these properties.
The different concentration of boron powder between 5% and 20% by weight containing each polymers to absorb the low energy secondary neutrons. Atomic parameters displayed in Table 1 (Kim et al. 1994). In the following Table 1, the details of each materials is given.
Table 1
Materials Names, Density, Chemical Formula, and Atomic parameters for Boron containing polymers from (Kim et al. 1994)
Materials
|
Atomic Parameters
|
Atom Density, 1022 atoms/g
|
Elements
|
Z
|
A
|
5% B
(ρ = 1.30 g/cm3)
|
10% B
(ρ = 1.33 g/cm3)
|
15% B
(ρ = 1.36 g/cm3)
|
20% B
(ρ = 1.40 g/cm3)
|
Pure Polyetherimide
(C37H24O6N2)
(ρ = 1.27 g/cm3)
|
H
|
1
|
1
|
23.2
|
22.0
|
20.7
|
19.5
|
C
|
6
|
12
|
35.8
|
33.8
|
32.0
|
30.1
|
N
|
7
|
14
|
1.93
|
1.83
|
1.73
|
1.63
|
O
|
8
|
16
|
5.80
|
5.49
|
5.18
|
4.88
|
B
|
5
|
11
|
2.23
|
4.46
|
6.69
|
8.93
|
B
|
5
|
10
|
0.558
|
1.11
|
1.67
|
2.23
|
|
Elements
|
Z
|
A
|
5% B
(ρ = 1.27 g/cm3)
|
10% B
(ρ = 1.30 g/cm3)
|
15% B
(ρ = 1.34 g/cm3)
|
20% B
(ρ = 1.37 g/cm3)
|
Pure Polysulfone
(C27H26O6S)
(ρ = 1.24 g/cm3)
|
H
|
1
|
1
|
28.6
|
27.0
|
25.5
|
24.1
|
C
|
6
|
12
|
35.0
|
33.1
|
31.3
|
29.6
|
O
|
8
|
16
|
5.19
|
4.90
|
4.63
|
4.38
|
S
|
16
|
32
|
1.30
|
1.22
|
1.16
|
1.10
|
B
|
5
|
11
|
2.11
|
4.46
|
6.66
|
8.76
|
B
|
5
|
10
|
0.527
|
1.12
|
1.66
|
2.20
|
|
Elements
|
Z
|
A
|
5% B
(ρ = 1.45 g/cm3)
|
10% B
(ρ = 1.48 g/cm3)
|
15% B
(ρ = 1.51 g/cm3)
|
20% B
(ρ = 1.54 g/cm3)
|
Pure Polyimide
(C35H28N2O7)
(ρ = 1.42 g/cm3)
|
H
|
1
|
1
|
15.0
|
14.2
|
13.4
|
12.6
|
C
|
6
|
12
|
33.0
|
31.2
|
29.4
|
27.7
|
N
|
7
|
14
|
3.0
|
2.84
|
2.67
|
2.52
|
O
|
8
|
16
|
7.52
|
7.10
|
6.69
|
6.31
|
B
|
5
|
11
|
2.15
|
4.46
|
6.82
|
8.9
|
B
|
5
|
10
|
0.538
|
1.12
|
1.7
|
2.23
|
GCR Model
One of the best ways to shield humans from high-energy radiation is to use material barriers. Transport codes may be used to measure the performance of various materials such as shields. The NASA Langley Research Center researchers have developed HZETRN, a typical deterministic method for solving the Boltzmann Transport Equation (Wilson et al. 2006). It uses a one-dimensional method to compute the interaction of both main and secondary particles. This differential equation is solved directly using a straight-ahead approximation, which implies that the primary ions' initial paths are still followed by the secondary particles created in the collision (Yang and Bayazitoglu 2020). As mentioned above the selected BO-2014 GCR model for 2010 solar minimum GCR event, which is occur at 1 AU in deep space.
To generate the nuclear data from the code, it requires some data inputs, which need to be generated. The execution mode, material name, density (g/cm3), number of atomic species, mass, charge, and number density (atoms/g) of the material are all defined in the input file for HZETRN. As a result, cross-section databases are created and stored in the cross section databases directory for a variety of shielding materials. Using this generated database it calculates the different parameters in output file. The output file contains a material definition file, the material's atomic cross-section database, a heavy ion nuclear cross-section database, a light particle nuclear cross-section database, isotropic source cross-section database using slab/3D transport for the same radiation environments, and databases for heavy ion, light particle, and isotropic source nuclear cross-sections. Flux as a function of energy at each depth, linear energy transfer (LET), dose, boundary condition, dose equivalent using ICRP 26 and ICRP 60 conversion coefficients, and dose equivalent using NASA quality factor for leukaemia and solid cancer all the response functions are simulated using HZETRN. In this work, we used the ICRP 60 conversion coefficients to simulate Dose Equivalent, LET, and Fluxes.
Simulation Geometry
In this analysis, each slab's thickness was adjusted to 5 g/cm2 for the 2010 solar minimum GCR condition, and all hydrogen-rich boron-containing polymer composite shielding materials were simulated using the slabs mode with a total shielding material thickness ranging from 0 to 100 g/cm2. In addition, an Aluminium slab of 10 g/cm2 followed by the various polymers composites materials slabs of 90 g/cm2 in a Multi-layered approach. We simulated fraction of dose equivalent by various particle types, LET, and Flux of neutron particle using HZETRN for 2010 solar minimum GCR.