American Institute of Aeronautics and Astronautics
1
Mitigating the Effects of the Space Radiation Environment: A Novel Approach of Using Graded-Z Materials
William Atwell1
Boeing Research & Technology (BR&T), Houston, TX 77058
Kristina Rojdev2 NASA Johnson Space Center, Houston, TX 77058
Sukesh Aghara3 and Sirikul Sriprisan4 University of Massachusetts Lowell, Lowell, MA 01854
In this paper we present a novel space radiation shielding approach using various material lay-ups, called “Graded-Z” shielding, which could optimize cost, weight, and safety while mitigating the radiation exposures from the trapped radiation and solar proton environments, as well as the galactic cosmic radiation (GCR) environment, to humans and electronics. In addition, a validation and verification (V&V) was performed using two different high energy particle transport/dose codes (MCNPX & HZETRN). Inherently, we know that materials having high-hydrogen content are very good space radiation shielding materials. Graded-Z material lay-ups are very good trapped electron mitigators for medium earth orbit (MEO) and geostationary earth orbit (GEO). In addition, secondary particles, namely neutrons, are produced as the primary particles penetrate a spacecraft, which can have deleterious effects to both humans and electronics. The use of “dopants,” such as beryllium, boron, and lithium, impregnated in other shielding materials provides a means of absorbing the secondary neutrons. Several examples of optimized Graded-Z shielding lay-ups that include the use of composite materials are presented and discussed in detail. This parametric shielding study is an extension of some earlier pioneering work we (William Atwell and Kristina Rojdev) performed in 20041 and 20092.
Nomenclature GCR = galactic cosmic radiation GEO = geostationary earth orbit HZETRN = High Z and Energy Transport code MCNPX = Monte Carlo Nuclear Particle transport computer code MEO = medium earth orbit V & V = validation & verification
I. Introduction
RADED-Z shielding is a laminate of several materials with different Z values (atomic numbers) designed to protect against ionizing radiation. Compared to single-material shielding, the same mass of Graded-Z shielding has been shown to reduce electron penetration over 60%.3 Graded-Z shielding is commonly used in satellite-
based particle detectors and offers several benefits: protection from radiation damage, reduction of background noise for detectors, and lower mass compared to single-material shielding. Designs vary, but typically involve a gradient
1 Technical Fellow, Boeing Research & Technology, 13100 Space Center Blvd./HB 2-30, AIAA Associate Fellow. 2 Engineer, Systems Architecture and Integration Office, 2101 NASA Parkway, MC: EA-361, AIAA Student Member. 3 Associate Professor, Chemical Engineering (Nuclear), 1 University Ave., Perry Hall – 318. 4 Research Associate, Chemical Engineering (Nuclear), 1 University Ave., Perry Hall – 318.
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https://ntrs.nasa.gov/search.jsp?R=20140002469 2020-06-11T16:52:03+00:00Z
American Institute of Aeronautics and Astronautics
2
from high-Z (usually tantalum [Ta]) through successively lower-Z elements such as tin, steel, and copper, usually ending with aluminum. Sometimes even lighter materials such as polypropylene and boron carbide are used.4,5 In a typical Graded-Z shield, the high-Z layer effectively scatters protons and electrons. It also absorbs gamma rays, which produces x-ray fluorescence. Each subsequent layer absorbs the X-ray fluorescence of the previous material, eventually reducing the energy to a suitable level. Each decrease in energy produces bremsstrahlung and Auger electrons, which are below the detector's energy threshold. Some designs also include an outer layer of aluminum, which may simply be the outer structure of a spacecraft or satellite. Fan, et al.6 reports “Shielding for space microelectronics needs to provide an acceptable dose rate with minimum shield mass. The analysis presented here shows that the best approach is, in general, to use a graded-Z shield, with a high-Z layer sandwiched between two low-Z materials. A Graded-Z shield is shown to reduce the electron dose rate by more than sixty percent over a single-material shield of the same areal density. For protons, the optimal shield would consist of a single, low-Z material layer. However, it is shown that a Graded-Z shield is nearly as effective as a single-material shield, as long as a low-Z layer is located adjacent to the microelectronics. A specific shield design depends upon the details of the radiation environment, system model, design margins/levels, compatibility of shield materials, etc.” In this paper we investigate several novel Graded-Z materials that are compared with baseline materials: aluminum (Al), high density polyethylene (HDPE), and water (H2O). In addition, we compare the results using two different computational computer codes, NASA HZETRN7 and MCNPX8 to validate and verify our results.
II. Study Assumptions
A. Graded-Z configurations The shielding configurations considered in this paper were two-layer shields with typical shielding thicknesses
and very large thickness configurations. The two layer shielding configurations were Al-HDPE, Ta-HDPE, and W-HDPE. The thicknesses of Al, Ta, and W were 150 mils, which correspond to 1.0287, 6.3237, and 7.3343 g/cm2, respectively, and the HDPE thicknesses were 5 and 10 g/cm2. The very large thickness configurations consisted of single layer H2O and two-layer H2O-SWX. SWX, specifically SWX-210, is a boron-doped hydrocarbon having a density of 1.19 g/cm3. The water thicknesses ranged from 100-300 g/cm2, and the SWX thicknesses were 10 and 20 g/cm2.
B. Environments For deep-space exploratory missions, the radiation sources are due to the naturally-occurring galactic cosmic
radiation (GCR) and from solar particle events (SPEs). The radiation exposure analyses discussed later is based on the GCR environment during solar minimum (epoch 1977), solar maximum (epoch 1982), and the classic series of solar proton events that occurred 19-24 October 1989. The October 1989 SPEs were four events that were combined using the Band fit.9,10 For all three environment cases, the energy spectrum was restricted to 2 GeV due to limitations in the MCNPX software, as shown in the differential energy spectrum below (Figure 1).
American Institute of Aeronautics and Astronautics
3
Figure 1. The Band fit differential energy spectrum for the 19-24 October 1989 SPEs.
C. High Energy Particle Transport/Dose Codes Two high energy particle transport/dose codes were used in the computations, HZETRN7 and MCNPX8, and the
results were compared as a check on the verification and validation of the absorbed doses. The HZETRN code was develop at NASA Langley Research Center in 1995. The high-charge-and energy (HZE) transport computer program HZETRN was developed to address the problems of free-space radiation transport and shielding. The HZETRN program is intended specifically for the design engineer who is interested in obtaining fast and accurate dosimetric information for the design and construction of space modules and devices. The program is based on a one-dimensional space-marching formulation of the Boltzmann transport equation with a straight-ahead approximation. The effect of the long-range Coulomb force and electron interaction is treated as a continuous slowing-down process. Atomic (electronic) stopping power coefficients with energies above a few MeV are calculated by using Bethe`s theory including Bragg`s rule, Ziegler`s shell corrections, and effective charge. Nuclear absorption cross sections are obtained from fits to quantum calculations and total cross sections are obtained with a Ramsauer formalism. Nuclear fragmentation cross sections are calculated with a semi-empirical abrasion-ablation fragmentation model. The relation of the final computer code to the Boltzmann equation is discussed in the context of simplifying assumptions.
The MCNPX code was developed at Los Alamos National Laboratory (LANL) and is described at their website11 as “MCNP is a general-purpose Monte Carlo N-Particle code that can be used for neutron, photon, electron, or coupled neutron/photon/electron transport. Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, detector design and analysis, nuclear oil well logging, accelerator target design, fission and fusion reactor design, decontamination and decommissioning. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and fourth-degree elliptical tori. Point-wise cross-section data typically are used, although group-wise data also are available. For neutrons, all reactions given in a particular cross-section evaluation (such as ENDF/B-VI) are accounted for. Thermal neutrons are described by both the free gas and S(alpha,beta) models. For photons, the code accounts for incoherent and coherent scattering, the possibility of fluorescent emission after photoelectric absorption, absorption in pair production with local emission of annihilation radiation, and bremsstrahlung. A continuous-slowing-down model is used for electron transport that includes positrons, x-rays, and bremsstrahlung but does not include external or self-induced fields. Important standard features that make MCNP very versatile and easy to use include a powerful general source, criticality source, and surface source; both geometry and output tally plotters; a rich collection of variance reduction techniques; a flexible tally structure; and an extensive collection of cross-section data. MCNP contains numerous flexible tallies: surface current & flux, volume flux (track length), point or ring detectors, particle heating, fission heating, pulse height tally for energy or charge deposition, mesh tallies, and radiography tallies.”
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1Bartholet, BEnergy Spac 2AtwellComputatio16 July 200
3Fan, WNo. 6, 1996
4Smith, 5Pia, M
3649. 6Fan, W
IEEE Trans7Wilson
and TripathNASA Techn
8MCNP
tudy investigatowed some slient. Howeverwith a single la
erification and ween the codeselucidate why rmore, since td whether thee and how thions is importaration, but de In addition,
s over two-laye
B., Atwell, W., ce Radiation Env, W., Boeder, nal and Experim9.
W.C., et al., "Shie, pp. 2790–2796D.M., et al., “Th. G., et al., "PIX
W. C., Drumm, Csactions in Nuclen, J. W., Badavi,hi, R.K., “HZETnical Paper 349
PX, http://en.wik
Americ
Table 3.
ted the use of ight dose redu, the Graded-Zayer of HDPE.
validation shs were due to kthere are largerthis study has e incident radhis will affectant because if wcrease the ovefuture work w
er or single-lay
Clowdsley, M., vironment,” SPAP., Wilkins, R
mental Results,”
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XE Simulation w
C. R., Roeske, Sear Science, Vol, F. F., CucinottTRN: Descriptio5, 1995.
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Dose values fo
IV.f Graded-Z mauctions in usinZ configuratio In the very la
howed similar known discrepr differences foonly focused
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we can acquireerall mass of will also inve
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Reddell, B., andACE-2004, San D
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S. B., and Scriv. 43, No. 6, 1996ta, F. A., Shinn,on of a Free-Sp
/MCNPX
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or 1982 GCR
Conclusionsaterials for radng Tantalum oon was actuallarge thickness ctrends betwee
pancies in methor the GCR sold on the dose,ns) or the proquivalent. Fu comparable rathe system, tstigate three-l
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