Applied Radiation and Isotopes 81 (2013) 190–195

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Applied Radiation and Isotopes

0969-80http://d

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journal homepage: www.elsevier.com/locate/apradiso

Development of an environmental radiation analysis researchcapability in the UAE

Sung-yeop Kim a,b, Chankyu Kim a,b, Kun Jai Lee a,b, Soon Heung Chang b,Hasna Elmasri a, Philip A. Beeley a,n

a Khalifa University of Science, Technology & Research, P.O. Box 127788, Abu Dhabi, United Arab Emiratesb Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701, Republic of Korea

H I G H L I G H T S

� New university environmental radiation laboratory established in UAE.

� Facilities included for alpha, beta and gamma radiometrics.� Transport modeling capability is being established.� Laboratory also used for education and training.� Robotic methods for sampling and analysis are under development.

a r t i c l e i n f o a b s t r a c t

Available online 26 March 2013

Keywords:Environmental radiation analysisRadiological dose assessmentRadiation measurementRadionuclide transport model

43/$ - see front matter & 2013 Elsevier Ltd. Ax.doi.org/10.1016/j.apradiso.2013.03.055

esponding author. Tel.: þ971 2 4018011; fax:ail address: philip.beeley@kustar.ac.ae (P.A. Be

The UAE has started a nuclear energy program with the aim of having its first four units on-line between2017 and 2020 and it is important that the country has an environmental radiation analysis capability tosupport this program. Khalifa University is therefore implementing a research laboratory to support bothexperimental analysis and radionuclide transport modeling in the aquatic and terrestrial environment.This paper outlines the development of this capability as well as the work in progress and planned for thefuture.

& 2013 Elsevier Ltd. All rights reserved.

1. Introduction

In December 2009 the Governments of the United Arab Emirates(UAE) and the Republic of Korea (ROK) signed an agreement thatwill result in the deployment of four 1400 MWe Advanced PowerReactor (APR 1400) in the Emirate of Abu Dhabi between 2017 and2020 and construction is due to start during 2012. This introduc-tion of nuclear energy into the UAE from a baseline of no previousnuclear fission related activities has resulted in an enormouscapacity building undertaking in all the technical areas necessaryto support the nuclear energy program, including environmentalradiometrics. Environmental radiation mapping has been carriedout within neighboring Gulf countries and surrounding areas andrecent radiation mapping reported for Kuwait (Jakes et al., 2008),Saudi Arabia (Al-Kheliewi et al., 2002), the Gulf of Aqaba (Ababnehet al., 2010) and Iran (Abdi et al., 2006) provide useful insight.Fig. 1 shows the Barakah Nuclear Power Plant (NPP) site locationfor the four APR 1400 reactors.

ll rights reserved.

þ971 2 4472442.eley).

Within this context, Khalifa University has established anuclear engineering department, tasked with providing the grad-uates required for the nuclear operator, regulator and all otheragencies charged with ensuring the safe and peaceful use ofnuclear energy within the country. Amongst the portfolio ofnuclear courses and research activities offered by the departmentis the provision of radiological environmental impact assessmenteducation and research training and a concerted effort is nowunderway to establish an environmental radiation analysis cap-ability. This paper describes the scope and activities being under-taken to establish this capability.

1.1. Scope

In defining the scope from the university perspective it isimportant to understand the context in the UAE. Prior to embark-ing on the UAE nuclear energy program the responsibility for theradiation in the environment lay within the Ministry of theEnvironment and Water and within the Emirate of Abu Dhabi,with the Environment Agency. This responsibility extended to theFederal Authority for Nuclear Regulation (FANR) upon its creationin September 2009, who now has overall responsibility for regulation

S-y. Kim et al. / Applied Radiation and Isotopes 81 (2013) 190–195 191

in the nuclear sector, including radiation safety. FANR is thereforein the process of creating the national environmental radiationlaboratory and the entities above will be amongst our keystakeholders.

From an education and research perspective the scope ofactivities for the university environment and waste managementresearch group covers the following areas:

�

Fig.

Sources of radiation in the environment;

� radiation metrology, including sampling and preparation

methodologies;

� transport of radiation in the terrestrial environment; � transport of radiation in the aquatic environment; � the application of robotics for radiometrics in harsh

environments;

� atmospheric transport modeling; � assessment and management of radiation release and impact

on the environment;

� accident release and countermeasures.

2. Defining the analytical requirements

The sources of environmental radiation are well known anddocumented extensively in the literature. Natural radioactivitycomprises the primordial radionuclides and man-made radio-nuclides from weapons testing and nuclear accidents, nuclear fuelcycle activities, industrial and medical uses of radiation, this lattergroup often termed the anthropogenic radionuclides. Given thatthe UAE is a major oil producing nation, Naturally OccurringRadioactive Material (NORM) and especially technology enhancedNORM, originating from oil exploration and production, will be a

1. Map of the United Arab Emirates showing location of the Barakah NPP Site.

Table 1The list of environmental radiation radionuclides.

Radionuclide Half-life M

Thorium-228 1.91 year AThorium-232 1.40�1010 year AUranium-234 2.46�105 year AUranium-235 7.04�108 year AUranium-238 4.47�109 year ARadium-226 1.60�103 year ARadium-228 5.75 year BeRadon-222 3.82 day ALead-210 22.2 year APolonium-210 138 day APotassium-40 1.25�109 year BeCesium-137 30.1 year BeStrontium-90 28.8 year BeKrypton-85 10.8 year BeCarbon-14 5.70�103 year BeTritium 12.3 year Be

study area. Table 1 lists the main radionuclides considered inchoosing the initial equipment for the environmental radiationlaboratory.

2.1. Equipment

In general, the amount of naturally occurring backgroundradiation is very low. For this reason, the detection and analysisof such radiation is very difficult and requires long time measure-ment. To analyze and assess the environmental radiation and theirorigin, radiation detectors with high sensitivity and performanceare required. For this purpose solely, three types of radiationdetectors are currently installed in the Environmental RadiationLaboratory of Khalifa University. Table 2 shows the specification ofthese 3 instruments. These instruments were chosen carefully todetect very low level of the three major types of environmentalradiation, namely; Gamma, Beta and Alpha radiation. All radiationdetectors are calibrated with standard sources and where neces-sary, Monte Carlo models are used for geometry corrections.

The radiation detectors at Khalifa University are all set andready for conducting measurements. As with any radiation detec-tors in any analytical laboratory, equipment for preparing samples,a prerequisite for some detectors prior to measurement, such asdrying, sieving, milling, ashing etc., are currently underway.

2.2. Sample preparation and measurement

The development of a manual for environmental sample pre-paration is also in progress. The manual is based on the referencefrom the (Korea Institute of Nuclear Safety, Safety, 2010) and theEnvironmental Measurements Laboratory of US Departmentof Energy (Erickson et al., 1997). The Environmental SamplePreparation Manual deals with soil, water (ground, underground,sea), grass, sea fish, milk and describes all procedures from thecollection of environmental sample to the analysis and assessmentof radionuclides included.

Currently some measurements and analysis are being per-formed for some samples from the International Atomic EnergyAgency (IAEA) and the US DOE at the Environmental RadiationLaboratory of Khalifa University. The laboratory received eighttypes of IAEA standard samples and a US DOE/Mixed AnalytePerformance Evaluation Program (MAPEP) performance evalua-tion sample. Table 3 shows the list of these samples.

The analysis for the IAEA standards was performed using the40% HPGe detector and results are compared against publishedresults of IAEA standards. This procedure is essential to testreliability of calibration with any detection system to be used for

ajor radiation Origin

lpha, Gamma Naturallpha, Gamma Naturallpha, Gamma Naturallpha, Gamma Naturallpha, Gamma Naturallpha, Gamma Naturalta, Gamma Naturallpha, Gamma Naturallpha, Beta, Gamma Naturallpha, Gamma Naturalta, Gamma Naturalta, Gamma Fission productta Fission productta, Gamma Fission productta Neutron activation productta Neutron activation product

Table 2Specification of 3 detectors for the environmental radiation analyses in UAE.

Instrument Manufacturer and model Specification

High Purity Germanium (HPGe) detectorsfor Gamma detection

ORTEC GEM40P4/ORTECGEM60P4

– Energy resolution: 1.85 keV for 1.33 MeV peak of 60Co– Low background level: shielded by ORTEC standard lead shields– Detection efficiency: 40% and 60% each– Electrical cooling system– Robotic sample changer for the 40% HPGe detector– Calibrated with standard Marinelli beaker.

Low background Alpha/Beta gas flowproportionalcounter for Alpha/Beta detection

Protean Instruments WPC1050

– Ultra low background detection: 0.1 cpm,for Alpha, 0.9 cpm for Beta– Detection efficiency: 40% for 210Po/231Am/230Th/137Cs, 35% for 99Tc and 55% for 90Sr/90Y– Automatic sample changing mechanism– Calibrated with the standard alpha and beta sources suitable in shape for use in such

equipment.

Liquid scintillation counter (LSC) for theanalysis of Tritium and Carbon-14

Perkin Elmer LSC-Tri-Carb3110 TR

– High detection efficiency: 60% for 3H, 95% for 14C– Programmed automatic sample changing function– Calibrated with the standard 3H and 14C sources.

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analysis of this nature. Only after a high degree of confidence inresults of IAEA standards, analysis for the soil sample in theMAPEP Program (Marlette, 2012) of DOE can be done. Thereliability of analysis results from the IAEA standard referencesamples and DOE sample is verified by comparison with referenceresults from other analysis groups in various laboratories indifferent locations in the world.

3. Transport modeling

The requirements for transport modeling will include bothterrestrial and aquatic regimes. In both cases a number of codesare being collected into our portfolio, as described in the followingsections and collaborative research projects will be undertaken.

3.1. Terrestrial transport

When we consider and simulate the terrestrial transport ofradionuclides and atmospheric transport pathway are the primarytransport pathway and mechanism to be focused on. Both themovement of radionuclides by wind and the dispersion of radio-nuclides by mixing with ambient air must be taken into account.Most of the models for simulation have been based on Gaussiandistribution calculated by Gaussian plume equation.

HotSpot is a simple Gaussian model from National AtmosphericRelease Advisory Center (NALAC) of Lawrence Livermore NationalLaboratory (LLNL). The most commonly used concepts areincluded to complete HotSpot code like Pasquill atmosphericstability classes, dry deposition, wet deposition, ground shine,etc. Library of isotopes with Dose Conversion Factors (DCFs)recommended by the International Commission on RadiologicalProtection (ICRP) is well prepared for calculating the both acuteand stochastic health effects (Homann, 2011). From above char-acteristics of this code, HotSpot is appreciated as appropriateeducational software even though results from this model areonly reliable for short range (less than 10 km) transport as asimple Gaussian model and simple wind and meteorologicalconditions can be input. Students can learn a variety of transportand exposure pathways with various modes like explosion, fire,resuspension, and general plume (Homann, 2011). For the researchinterest, HotSpot is a useful code for calculating short term and

short range atmospheric dispersion spending short time and lesseffort.

WinMACCS is an integrated code with an updated version ofMACCS2 (MELCOR Accident Consequence Code Systems 2),COMIDA2, and LHS (Latin Hypercube Sampling) and can be rununder Windows operating system. The components of WinMACCSare described in Fig. 2. MACCS2 was developed at Sandia NationalLaboratories (SNL) for the US Nuclear Regulatory Commission(NRC) to simulate the impact of severe accidents at nuclear powerplants on the surrounding environment (McFadden et al., 2007).MACCS2 is composed of ATMOS, EARLY, and CHRONC and each ofthe three code modules performs phenomenological modeling(Chanin et al., 1998). Table 4 shows the phenomenological modelsof each of the modules. COMIDA2 is the module for food chaincalculation and LHS is used to perform uncertainty analysis(McFadden et al., 2007). WinMACCS code can perform as the codethat is faithful to the basics. For the aspect of research, WinMACCShas the advantage that user can carry out whole process of NPPsafety analysis from source term analysis to mitigative actions planlike evacuation and economic cost analysis.

ADMS4 (Atmospheric Dispersion Modeling System) fromCambridge Environmental Research Consultants (CERC) is one ofthe candidate codes to if more detailed and advanced atmospherictransport code is needed for the research perspective. Complexsource/terrain geometry can be simulated by ADMS4 and it isbased on current understanding of the atmospheric boundarylayer characterized by the boundary layer depth and Monin–Obukhov length rather than in terms of the single parameterPasquill–Gifford class and reliability for far field transport is higherthan simple Gaussian model using a skewed Gaussian concentra-tion distribution to calculate dispersion under convective condi-tions (Cambridge Environmental Research Consultant, 2010). Userfriendly window based interface is well prepared for ADMS 4 andit is installing good visualization tool.

AERMOD modeling system (US EPA, 2004) from US Environ-mental Protection Agency (EPA) is a steady-state plume model andCALPUFF modeling system developed by Atmospheric StudiesGroup (ASG) at TRC is a non-steady-state puff dispersion modeland both of AERMOD and CALPUFF are recommended modelingsystem from US EPA and are comprised of detailed preprocessingand post processing programs. For example, the CALPUFF model-ing system is including CALMET as a diagnostic 3-dimensionalmeteorological model, CALPUFF as an air quality dispersion model,

Table 3The list of IAEA reference samples and a US DOE/mixed analyte performance evaluation program (MAPEP) performance evaluation sample used for calibrations atKhalifa University.

Sample Quantity Description Contained radionuclides

IAEA-321 1 Milk Powder, 250 g 40K, 90Sr, 134Cs, 137Cs

IAEA-444 2 Soil, 200 g 54Mn, 60Co, 65Zn, 109Cd, 134Cs, 137Cs, 210Pb, 241AmIAEA–312 3 Soil, 50 g 226Ra, Th, U

IAEA-434 2 Phosphogypsum, 250 g 210Pb, 226Ra, 230Th, 234U, 238U

IAEA-447 1 Moss Soil 137Cs, 208Tl, 210Pb, 210Po, 212Pb, 214Pb, 214Bi, 226Ra, 228Ac, 234Th, 234U, 238U, 238Pu, 239þ240Pu, 241Am

IAEA-385 2 Radionuclides in Irish Sea Sediment 40K, 137Cs, 226Ra, 228Ra, 230Th, 232Th, 234U, 238U, 238Pu, 239þ240Pu, 241Am

IAEA–414 2 Radionuclides in Sea Fish 40K, 137Cs, 232Th, 234U, 235U, 238U, 238Pu, 239þ240Pu, 241Am

IAEA-372 2 Radionuclides in Grass 40K, 137Cs

MAPEP-11-Ra226/U238

1 Soil, 800 g 226Ra, 238U

Fig. 2. Components of the WINMACCS code for calculating dispersion of radionuclides after an accident (McFadden et al., 2007).

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and CALPOST as a post processing package (Scire et al., 2000).Those modeling systems can be utilized by Khalifa University forthe simulation in complicated meteorological condition and com-plex terrain condition.

3.2. Aquatic transport

The necessity for aquatic transport modeling in support of anuclear power program is important, as demonstrated by theFukushima nuclear incidents and model simulations of the impactare now appearing in the scientific literature (Behrens et al., 2012).With respect to developing a capability for dispersion modeling ofradioactive liquid effluents, to support the Barakah NPP sites onthe Arabian Gulf, methodologies used for Wolsong NPP site inKorea (Lee et al., 2011) and modeling of the consequences ofhypothetical accident releases in a gulf type of region (Krylov andPavlovski, 2009) have been considered. An initial capability istherefore being developed using the Princeton Ocean model(POM) (Mellor, 2004) and the Environmental Fluid Dynamic Code(EFDC) (Hamrick, 1992).

A more medium/long term capability is to use an unstructuredfluid model, such as the Imperial College Ocean Model, Fluidity/ICOM (Pain et al., 2005) which can simultaneously resolve bothsmall and large scale ocean flows while conforming with theresolution required for complex coastlines and bathymetry.

RESRAD (Version 6) is the family of code to assess theenvironmental impact assessment from contaminated soil sourcedeveloped from Environmental Assessment Division, ArgonneNational Lab (ANL) and sponsored by US DOE. RESRAD is con-sidering both of the atmospheric and aquatic transportation ofradionuclides and can calculate the dose from both of externalexposure and internal exposure (Argonne National Laboratory,2001). This code is appraised as a good educational code toeducate about the dose from the contaminated soil because mostof exposure pathways are included, those are external radiation,inhalation, and ingestion. Fig. 3 shows the schematic representa-tion of RESRAD pathways. The DCFs from EPA's Federal GuidanceReport (FGR) no 11, 12, and 13 and radionuclides information fromICRP is well applied to this code (Argonne National Laboratory,2001), from this reason, this code is useful to introduce abouthealth physics to students.

Table 4Phenomenological models of ATMOS, EARLY, and CHRONC (Chanin et al., 1998).

The ATMOS Module: Atmospheric Transport and Deposition Source Term SpecificationWeather DataRisk-Dominant PlumeInitial Plume DimensionsRepresentative Weather PointDownwind TransportPlume RiseDispersion—Gaussian Plume ModelOverview of Plume DepletionDepletion by Radioactive DecayDepletion by Dry DepositionDepletion by Wet DepositionCenterline Air and Ground Concentrations

The EARLY Module: Emergency-Phase Calculations Overview of Exposure PathwaysOff-Centerline Correction FactorCloudshineGroundshineDirect InhalationResuspension InhalationEmergency-Phase Relocation CostsEvacuationShelteringDose-Dependent RelocationAcute Health Effects—Early Fatality and Early Injury ModelsCancer Health Effect Models

The CHRONC Module: Intermediate- and Long-Term-Phase Calculation Overview of Exposure PathwaysOff-Centerline Correction FactorGroundshineResuspension InhalationCOMIDA2 Model for Food IngestionMACCS Model for Food IngestionWater IngestionMitigative Action ModelsEconomic Costs from Intermediate PhaseEconomic Costs from Long-Term Phase

Fig. 3. Schematic representation of RESRAD pathways for calculating final human dose (Argonne National Laboratory, 2001).

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GoldSim from GoldSim Technology Group (GTG) is flexiblesoftware to simulate aquatic transport pathway and biospherewith GoldSim Radionuclide Transport module (GoldSim TechnologyGroup, 2010). This is not a model but a modeling tool. Themodel from this software is built by combining each functionalGoldSim elements by user. From this characteristic, user can

freely create his or her own model but user has to prepare andinput every detailed data. User-friend characteristic with wellprepared Graphic User Interface (GUI) is one of advantages ofGoldSim. This software is recommended to purchase when thedetailed models about aquatic transport and food chain areneeded, and it is important that detailed design and data have

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to assist to complete modeling. Furthermore, from the flex-ibility of creation of this software, educational model can bedeveloped by this software with permission from GTG.

4. Future developments

The sampling environment, both terrestrial and aquatic, in theUAE is harsh and while classical sampling techniques will be used,the opportunity to develop robotic methods is under considerationwithin the University's Robotics Research Institute and throughinternational collaborations.

With respect to experimental methods, documented analyticaltechniques will be used but adapted, where necessary, to deal withthe unique conditions in the region.

With aquatic modeling, it is important that both ground water,coastal and ocean transport are taken into consideration and thecodes described above have been chosen to address the appro-priate radiation pathways.

As defined in the scope of work, the capabilities under devel-opment will also be used in education and training of students inorder to develop appropriate radiation metrology capabilities inaccordance with best international practice.

5. Conclusions

The UAE is unique in embarking on a nuclear energy programfrom a starting position of virtually no nuclear science, engineer-ing or technology infrastructure in the country. Capacity buildingin all areas is therefore moving at pace the creation of anenvironmental radiation analysis research capability is importantfor the country. Khalifa University (KU) is developing this researchcapability as part of its requirement to support the human capacitybuilding for the key nuclear stakeholders. It is important to notethat laboratory for routine environmental radiation analysis willbe provided by FANR with appropriate technical assistance fromvarious parties; KU will complement this by providing a researchcapability, especially with respect to the unique features of sand,heat, wind and a saline and shallow gulf. The methodologiesdescribed above will therefore be designed to deal with theseunique regional conditions. It is also by intent that the environ-mental radiation laboratory will work on both experimentalmeasurements as well as radiation transport modeling and thepossible syntheses between these two areas.

Acknowledgments

This work is jointly funded by the Khalifa University and KAIST.The authors are grateful for helpful information and advice fromthe Korea Research Institute of Standards and Science (KRISS) and

Korea Institute of Nuclear Safety (KINS)—Environmental Radio-activity Assessment Department.

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