Determination of the cosmic-ray-induced neutron flux and ambient dose equivalent at flight altitude

Similar documents
CHARACTERIZATION OF A RADIATION DETECTOR FOR AIRCRAFT MEASUREMENTS

Geant4 Hadronic Physics Developments

Nuclear Cross-Section Measurements at the Manuel Lujan Jr. Neutron Scattering Center

Results obtained with nuclear models of Geant4 in IAEA Benchmark of Spallation

Analysis distribution of galactic cosmic rays particle energy with polar orbit satellite for Geant4 application

Geant4 Based Space Radiation Application for Planar and Spherical Geometries

Geant Hadronic Physics I. Geant4 Tutorial at Lund University. 6 September 2018 Dennis Wright

Geant4 simulations of neutron production in a thorium fuelled Accelerator Driven Subcritical Reactors

Validation of the UFS Bonner Sphere Spectrometer and Monte Carlo Methods at the CERN-EU high energy Reference Field (CERF)

Recent Developments in Pre-Equilibrium and De-Excitation Models in Geant4

Nuclear cross-section measurements at the Manuel Lujan Jr. Neutron Scattering Center. Michal Mocko

THE LHC, currently under construction at the European Organization

Geant4 version 10.0.p01. Hadronic Physics I. Geant4 Tutorial: version 10.0.p01. Michael Kelsey, Wed 5 Mar 2014

Chapter V: Interactions of neutrons with matter

Hadronic Physics I. University of Pennsylvania Geant4 Tutorial 17 May 2011 Dennis Wright. Geant4 V9.4

Comparison of Different INC Physical Models of MCNPX to Compute Spallation Neutronics of LBE Target

Recent Developments in Geant4 Hadronics. Geant4/Spenvis Workshop at JPL 6 November 2006 Dennis Wright

Detector Sensitivity

Correction for PMT temperature dependence of the LHCf calorimeters

INCL INTRA-NUCLEAR CASCADE AND ABLA DE-EXCITATION MODELS IN GEANT4

arxiv:nucl-th/ v1 2 Jun 2003

INCL Intra-Nuclear Cascade and ABLA De-Excitation Models in Geant4

Theoretical Assessment of Aircrew Exposure to Galactic Cosmic Radiation Using the FLUKA Monte Carlo Code

Benchmarking the CEM03.03 event generator

Fluence-to-Dose Conversion Coefficients for Muons and Pions Calculated Based on ICRP Publication 103 Using the PHITS Code

THE simulation of the production, interaction and transportion

Impact of the choice of physics list on GEANT4 simulations of hadronic showers in tungsten

Characterization of the 3 MeV Neutron Field for the Monoenergetic Fast Neutron Fluence Standard at the National Metrology Institute of Japan

Cross Running Head: Geant4 Hadronic Physics and the Geant4-DNA project.

Progress in Hadronic Physics Modeling in Geant4

Journal of Radiation Protection and Research

Recent Developments in Geant4 Hadronic Physics

Sequential Measurements of Cosmic-Ray Neutron Energy Spectrum and Ambient Dose Equivalent on the Ground

The vertical cut-off rigidity means that charged particle with rigidity below this value cannot reach the top of atmosphere because of the earth's

Improvements and developments of physics models in PHITS for radiotherapy and space applications

Nuclear contribution into single-event upset in 3D on-board electronics at moderate energy cosmic proton impact

External MC code : PHITS

Solar particle events contribution in the space radiation exposure on electronic equipment

Development of a Dosimetric System using Spectrometric Technique suitable for Operational Radiation Dose Measurements and Evaluation

Measuring dose equivalent in an aviation environment using PIN diodes

Update on Calibration Studies of the Canadian High-Energy Neutron Spectrometry System (CHENSS)

GEANT4 HADRONIC PHYSICS

Radiation Shielding Simulation For Interplanetary Manned Missions

Radiation Shielding Simulation For Interplanetary Manned Missions

Validation of the MCNP computational model for neutron flux distribution with the neutron activation analysis measurement

ICRP Symposium on the International System of Radiological Protection

Fast-Neutron Production via Break-Up of Deuterons and Fast-Neutron Dosimetry

Design, construction and characterization of a portable irradiator to calibrate installed ambient dose equivalent monitors

Photonuclear Reaction Cross Sections for Gallium Isotopes. Serkan Akkoyun 1, Tuncay Bayram 2

NEUTRON H*(10) INSIDE A PROTON THERAPY FACILITY: COMPARISON BETWEEN MONTE CARLO SIMULATIONS AND WENDI-2 MEASUREMENTS

Modelling moderated proportional neutron counters using the Geant4 toolkit and the application to detection of fast neutron burst

Geant4 simulation of SOI microdosimetry for radiation protection in space and aviation environments

Radiation Transport Tools for Space Applications: A Review

Altitude Variation of cosmic-ray neutron energy spectrum and ambient dose equivalent at Mt.Fuji in Japan

THE mono-energetic hadron beam such as heavy-ions or

Benchmark Test of JENDL High Energy File with MCNP

PHENIX measurements of bottom and charm quark production

Upcoming features in Serpent photon transport mode

Multiscale integral analysis of a HT leakage in a fusion nuclear power plant

Radiation safety of the Danish Center for Proton Therapy (DCPT) Lars Hjorth Præstegaard Dept. of Medical Physics, Aarhus University Hospital

Progress in Nuclear Science and Technology, Volume 6,

G4 vs. Fluka comparison for single neutron

Neutron Time-Of-Flight Spectrometer Based on HIRFL for Studies of Spallation Reactions Related to ADS Project

Estimation of Radioactivity and Residual Gamma-ray Dose around a Collimator at 3-GeV Proton Synchrotron Ring of J-PARC Facility

MCNP6 Simulation of Light and Medium Nuclei Fragmentation at Intermediate Energies

Monte Carlo Simulation concerning Particle Therapy

Validation of Geant4 Physics Models Using Collision Data from the LHC

JRPR. Measurement of Neutron Production Doubledifferential Cross-sections on Carbon Bombarded with 430 MeV/Nucleon Carbon Ions.

A generalized approach to model the spectra and radiation dose rate of solar particle events on the surface of Mars

3164 IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 55, NO. 6, DECEMBER /$ IEEE

Secondary Radiation and Shielding Design for Particle Therapy Facilities

Nuclear Spectroscopy: Radioactivity and Half Life

Validation of Geant4 Hadronic Physics Models at Intermediate Energies. Outline

Introduction. Neutron Effects NSEU. Neutron Testing Basics User Requirements Conclusions

November 2013 analysis of high energy electrons on the Japan Experimental Module (JEM: Kibo)

Benchmark of Nuclear Spallation Models

Effective dose calculation at flight altitudes with the newly computed yield function

596 IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 64, NO. 1, JANUARY 2017

Current and Recent ICRU Activities in Radiation Protection Dosimetry and Measurements

Neutron and Gamma-ray Emission Double Dierential Cross Sections. *5 Energy Conversion Engineering, Kyushu University, Kasuga-koen, Kasuga-shi 816.

Application and Validation of Event Generator in the PHITS Code for the Low-Energy Neutron-Induced Reactions

An industrial radiography exposure device based on measurement of transmitted gamma-ray intensity

Measurement of activation of helium gas by 238 U beam irradiation at about 11 A MeV

On the energy deposition by electrons in air and the accurate determination of the air-fluorescence yield

A Monte Carlo Simulation for Estimating of the Flux in a Novel Neutron Activation System using 252 Cf Source

Analysis of cosmic ray neutron-induced single-event phenomena

Precision neutron flux measurement with a neutron beam monitor

ISSCREM: International Space Station Cosmic Radiation Exposure Model

ON THE OMNIPRESENT BACKGROUND GAMMA RADIATION OF THE CONTINUOUS SPECTRUM

CLASSIFICATION AND IMAGING OF SPENT NUCLEAR FUEL DRY CASKS USING COSMIC RAY MUONS

Reconstruction of Neutron Cross-sections and Sampling

GAMMA-RAY ASTRONOMY: IMAGING ATMOSPHERIC CHERENKOV TECHNIQUE FABIO ZANDANEL - SESIONES CCD

Statistical Model Calculations for Neutron Radiative Capture Process

A Personal Use Program for Calculation of Aviation Route Doses

IAC-08-A MONTE CARLO SIMULATIONS OF ENERGY LOSSES BY SPACE PROTONS IN THE CRATER DETECTOR

Hands on LUNA: Detector Simulations with Geant4

Extension of CASCADE.04 to estimate neutron fluence and dose rates and its validation

Average value of available measurements of the absolute air-fluorescence yield

Energy response for high-energy neutrons of multi-functional electronic personal dosemeter

Recent Developments in Geant4. Calice Collaboration Meeting 10 March 2010 Dennis Wright (on behalf of the Geant4 hadronic working group)

Transcription:

Journal of Physics: Conference Series PAPER OPEN ACCESS Determination of the cosmic-ray-induced neutron flux and ambient dose equivalent at flight altitude To cite this article: M T Pazianotto et al 2015 J. Phys.: Conf. Ser. 630 012022 Related content - Quantities for environmental monitoring J A B Gibson, J A Dennis and J R Harvey - Calibration of protection-level instruments, conversion coefficients (Sv/Gy) for the ISO reference photon radiations I M G Thompson - Advice following ICRP Publication 60 The British Committee on Radiation Units and Measurements View the article online for updates and enhancements. This content was downloaded from IP address 46.3.201.74 on 22/11/2017 at 12:37

Determination of the cosmic-ray-induced neutron flux and ambient dose equivalent at flight altitude M T Pazianotto 1, M A Cortés-Giraldo 2, C A Federico 3, O L Gonçalez 3, J M Quesada 2, B V Carlson 1 1 Aeronautics Technological Institute, Physics Department, São José dos Campos, Brazil 2 University of Sevilla, Atomic, Molecular and Nuclear Physics Department, Sevilla, Spain 3 Institute for Advanced Studies, Applied Physics Department, São José dos Campos, Brazil E-mail: mpazianotto@gmail.com Abstract. There is interest in modeling the atmosphere in the South Atlantic Magnetic Anomaly in order to obtain information about the cosmic-ray induced neutron spectrum and angular distribution as functions of altitude. In this work we use the Monte Carlo codes MCNPX and Geant4 to determine the cosmic-ray-induced neutron flux in the atmosphere produced by the cosmic ray protons incident on the top of the atmosphere and to estimate the ambient dose equivalent rate as function of altitude. The results present a reasonable conformity to other codes (QARM and EXPACS) based on other parameterizations. 1. Introduction Great efforts are being made to understand the accumulated neutron dose at flight altitude in the South Atlantic Magnetic Anomaly (SAMA) [1,2], because a large part of Brazil, and therefore South America, are subject to this Anomaly. Figure 1 shows that the SAMA at 12 km altitude is located with its center point above Brazil, near Foz do Iguaçú city. Among the many particles produced by interactions between primary cosmic rays and atmospheric atoms, neutrons are the most important component to consider in order to assess the dose deposition in the crew members of an aircraft, as well as in electronic equipment, such as on-board computers [3]. Thus, there is great interest in modeling the atmosphere and simulating the cosmic-ray induced neutron spectrum at flight altitude to develop further applications for the study of their effects on microelectronic devices [4] and carry out dosimetry studies aboard aircrafts. The purpose of this work is to determine the cosmic-ray-induced neutron (CRINS) flux in the atmosphere produced by protons using the codes MCNPX [5] and Geant4 [6] and then to estimate the ambient dose equivalent rate (ADER) through the atmosphere. In this work, we are evaluating the Geant4 by comparing it with MCNPX and other codes in order to search possible effects of the Earth's magnetic field on the neutron flux as well on the ADER in flight altitude. The magnetic field can be easily included in Geant4, but not in MCNPX v2.5 and in the other codes used in this comparison. Content from this work may be used under the terms of the Creative Commons Attribution 3.0 licence. Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI. Published under licence by Ltd 1

Figure 1. Earth s magnetic field map at 12 km altitude, taken from [7]. 2. Methodology 2.1. Computational procedure Figure 2 shows the geometry of the atmosphere used in the simulations. The atmosphere was modeled as a cylinder of 50 km height and 25 km radius. For the sake of reproducing the variable density of the atmosphere at different altitudes, the cylinder was divided into layers of 2.5 km thickness below 12.5 km altitude, whereas 5 km layers where used above this altitude level. The air density and composition of each layer was set according to the International Standard Atmosphere [8]; the air humidity was also modeled below 12.5 km altitude [9]. In order to reproduce an infinite medium, we used fully reflective sidewalls of the cylinder for all the particles that impinge on them. We used a primary cosmic ray flux composed only of protons at the top of the cylinder. The primary proton spectrum was obtained from QARM [10] at the geographical coordinates -23.04 S -45.15 W and at the date June 06, 2009. Figure 2. Schematic figure of the atmosphere modeling for cosmic ray propagation. 2

2.2. MCNPX physics models In the simulations with MCNPX v2.5 the ENDF/VI nuclear data library was used for all materials. We considered the scattering matrices S(, ) [5, 11] to correct the hydrogen cross section in water, which is important for neutron transport at low energies. Nuclear data libraries were used for neutron energies under 20 MeV. Physical models were used above this energy range according to the following parameterizations: - Neutron and proton interaction only by elastic scattering; - Bertini intranuclear cascade for nucleons, followed by pre-equilibrium; - Coulomb barrier for incident charged particles; 2.3. Geant4 physics models The simulations were carried out with the version 9.6.3 and 9.6.2 of the GEANT4 toolkit. For incident energies above 10 GeV, the hadronic interactions have been modeled with the Quark-gluon String Model (QGS). At lower energies, which are the most relevant in the present work, we used either the same hadronic modeling (Bertini Model) as MCNPX in the intranuclear cascade phase, followed by preequilibrium (physics list QGSP_BERT_HP), or the Binary Cascade, followed by the Exciton Preequilibrium model and final equilibrium de-excitation with a variety of models (Weisskopf-Ewing evaporation of nucleons and light clusters, photon emission, fission, Fermi break-up and statistical multifragmentation) as final stages (physics list QGSP_BIC_HP). For the transport of neutrons below 20 MeV, the High Precision (HP) model with G4NDL4.0 data was used. 3. Results 3.1. Comparison between MCNPX and Geant4 Figure 3 shows the integral neutron flux as a function of altitude calculated with MCNPX and Geant4. The simulations were performed using an enough events so that the statistical errors are significantly smaller than the values of the simulated data. The agreement between the MCNPX and the Geant4 simulations with the QGSP_BERT_HP physics list is certainly due the fact that the Bertini intranuclear cascade model is used in both cases. However, the agreement with the calculations done with the QGSP_BIC_HP physics list is observed only at 5 km altitude. For altitudes higher than 5 km, the QGSP_BIC_HP simulations predict a lower neutron counting rate, whereas at lower altitudes the situation is the opposite, i.e., they produce a higher neutron counting compared to those of MCNPX and the QGSP_BERT_HP Geant4 physics list. As a preliminary analysis, the origin of this divergence could be traced back to the different neutron multiplicities of each model. At present, we are evaluating the primary proton integral flux as a function of altitude in an attempt to establish the connection between the number of neutrons produced and the protons absorbed throughout the atmosphere, which should provide us with a deeper understanding of this phenomenology. 3

Figure 3. Integral neutron flux calculated with MCNPX and Geant4 with QGSP_BIC_HP and QGSP_BERT_HP physics lists. Figure 4 shows the cosmic-ray induced neutron spectrum normalized per primary proton at 1 m (i.e., ground level) and 15 km altitude as simulated by MCNPX and Geant4 with the BIC and Bertini models. We observe a higher neutron production by spallation reactions at ground level with the Binary Cascade model of Geant4 than with the Bertini model. However, we have just the opposite at 15 km altitude. In the thermal region at 1 m altitude, the neutron flux simulated with Geant4 is lower than the one simulated with MCNPX. This fact could be also explained due to the different neutron multiplicity of each model as previously mentioned. Figure 4. Neutron spectrum calculated at 1 m and 15 km altitude with MCNPX and Geant4 with QGSP_BIC_HP and QGSP_BERT_HP physics lists. 4

Figure 5 compares the neutron flux calculated with MCNPX, GEANT4 (using QGSP_BIC_HP) and EXPACS [12] with the experimental data from Federico et al [2] measured at 1 m altitude in São José dos Campos and other experimental results taken from the Goldhagen et al [13]. The results were normalized to 1 neutron/cm 2 integral flux in order to analyze only the energy dependence of the neutron spectra. At the thermal peak there is a wide dispersion of results, where the experimental measurement of Federico et al. [2] shows the largest amplitude and the Geant4 simulation has the smallest amplitudes. However, the results of MCNPX, EXPACS and Goldhagen somewhat agree among themselves. As well as the previous results (Figure 4), the energy dependence of the MCNPX and Geant4 simulations reproduce well the shape of the spectrum between the thermal and evaporation peaks, and these, in turn, reproduces well the experimental results of Goldhagen et al [13], but overestimate the experimental results of Federico et al [2]. However, the spallation region is clearly overestimated in the MCNPX and Geant4 calculations. The divergence between these results could be explained by the concentration of water used in the simulations, since the relative height of the peaks depends strongly on this [14]. A deeper study of this dependence is being carried out. Figure 5. Energy dependence of the neutron flux at 1 m altitude calculated with EXPACS, MCNPX, GEANT4 and measured experimentally [3,12]. 3.2. Ambient dose equivalent rate as a function of altitude Figure 6 shows a comparison of the integral neutron flux per incident proton as a function of altitude between our Monte Carlo simulations with MCNPX and Geant4, and QARM code. The results present a reasonable conformity throughout for altitudes that ranges from 2.5 km to 15 km, but for ground level there is a divergence between our Monte Carlo simulations and QARM that could be explained due to the soil composition used on QARM code, information which could not be retrieved. 5

Figure 6. Absolute neutron flux as function of altitude determined by MCNPX, Geant4 and QARM. Figure 7 compares the ambient dose equivalent rate obtained with MCNPX, GEANT4 and QARM. In order to determine the ambient dose equivalent rate, we multiplied the CRINS spectra by the integral proton flux at the top the atmosphere to obtain the CRIN in absolute value and then multiplied these spectra by a conversion factor that can be found in the ICRP74 data [15]. From this figure it can be seen that there is a remarkable agreement at 10 km altitude between the three codes. QARM gives the highest equivalent ambient dose values at altitudes lower than 10 km, whereas at higher altitudes the values predicted with both Monte Carlo codes are higher than those of QARM; nevertheless, the agreement between the calculations is quite reasonable. Figure 7. Ambient dose equivalent rate as function of altitudes. As a first order approximation, we have initiated a study of the influence of Earth s magnetic field on the ambient dose equivalent rate. To do this, we have used the Geant4 code together with terrestrial 6

magnetic field data from [16] at the geographical coordinates 23.04 S 45.15 W on the date June 06, 2010, when its horizontal intensity was 18,528.8 nt. Figure 8 shows the comparison of the ADER considering the Earth s magnetic field and excluding it. The magnetic field does not change the ADER for altitudes between 1 m up to 45 km, where the air density is very low compared to the ground level. Ambient dose equivalent rate (microsv/h) 1.0 0.8 0.6 0.4 0.2 0.0 Without magnetic field With magnetic field 0 10 20 30 40 50 Altitude (km) Figure 8. Ambient dose rate versus altitude calculated with GEANT4. The Earth's magnetic field was turned on and off for comparison. 4. Conclusions The comparison between our Monte Carlo simulations with MCNPX (version 2.5) and Geant4 (version 9.6.2 and 9.6.3) and the calculations obtained with the codes QARM and EXPACS presents good general agreement, although a difference exists at 1 m altitude that could be explained by soil composition. For future work, a detailed analysis of the soil composition influence will be necessary. As a first order approximation, the Earth's Magnetic field does not change the ambient equivalent dose rate for altitudes up to 45 km. Ongoing studies with the Geant4 toolkit and analytical calculations are being performed to quantify the influence of the Earth's magnetic field on the primary and secondary particles throughout the atmosphere and on the particle angular distributions as a function of altitude. 7

References [1] Freden S C and Paulika G A 1964 Trapped protons at low altitudes in the South Atlantic magnetic anomaly Jour. of Geophysical Research vol 69 pp 1259-1269. [2] Federico C A et al 2010 Neutron spectra measurements in south Atlantic anomaly region Rad. Measurements vol. 45 pp 1526-1528 [3] Prado A C M et al 2013 Effects of cosmic radiation on devices and embedded systems in aircrafts 2013 International Nuclear Atlantic Conference [4] Pereira Junior E C F et al 2014 The effects of total ionizing dose on the neutron SEU cross section of a 130 nm 4 Mb SRAM memory Proc 15th Latin American Test Workshop [5] Pelowitz D 2005 MCNPX User's Manual Version 2.5.0 Los Alamos National Laboratory report LA-CP-05-0369 [6] Agostinelli S et al 2003 GEANT4 a simulation toolkit Nucl Instr Meth Phys Res A vol 506(3) pp 250-303 [7] Space Environment Iformation System. Available at: www.spenvis.oma.be. [8] International Organization for Standardization 1975 Standard Atmosphere ISO 2533:1975 1975 [9] Salby M L, Pielke R A, Dmowska R 1996 Fundamentals of Atmospheric Physics International Geophysics vol 61. [10] Lei F, Clucas S, Dyer C, Truscott P 2004 An atmospheric radiation model based on response matrices generated by detailed Monte Carlo Simulations of cosmic ray interactions IEEE Transactions on Nuclear Science vol 51 [11] Mattes M and Keinert J Thermal Neutron Scattering Data for the Moderator Materials H2O, D2O and ZrHx in ENDF-6 Format and as ACE Library for MCNP(X) Codes IAEA report INDC(NDS)-0470 [12] Sato T EXPACS User's Manual Japan Atomic Energy Agency [13] Goldhagen P et al 2002 Nucl Measurement of the energy spectrum of cosmic-ray induced neutrons aboard an ER-2 high-altitude airplane Nuclear Instruments and Methods in Physics Research A vol 476 2002 [14] Nakamura T et al 2005 Sequential measurements of cosmic-ray neutron spectrum and dose rate at sea level in Sendai Japan. J. Nucl. Sci. Technol. vol 42 [15] ICRP 1996 Conversion Coefficients for use in Radiological Protection against External Radiation ICRP Publication 74 Ann. ICRP 26 (3-4) [16] Earth s Magnetic Field Calculators. Available at: https://www.ngdc.noaa.gov/geomag/magfield.shtml 8