<?xml version="1.0" encoding="UTF-8"?><!DOCTYPE article  PUBLIC "-//NLM//DTD Journal Publishing DTD v3.0 20080202//EN" "http://dtd.nlm.nih.gov/publishing/3.0/journalpublishing3.dtd"><article xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink" dtd-version="3.0" xml:lang="en" article-type="research article"><front><journal-meta><journal-id journal-id-type="publisher-id">JASMI</journal-id><journal-title-group><journal-title>Journal of Analytical Sciences, Methods and Instrumentation</journal-title></journal-title-group><issn pub-type="epub">2164-2745</issn><publisher><publisher-name>Scientific Research Publishing</publisher-name></publisher></journal-meta><article-meta><article-id pub-id-type="doi">10.4236/jasmi.2019.92004</article-id><article-id pub-id-type="publisher-id">JASMI-92891</article-id><article-categories><subj-group subj-group-type="heading"><subject>Articles</subject></subj-group><subj-group subj-group-type="Discipline-v2"><subject>Chemistry&amp;Materials Science</subject></subj-group></article-categories><title-group><article-title>
 
 
  Precise Determination of Uranium Isotopes in Suez Canal Sediment
 
</article-title></title-group><contrib-group><contrib contrib-type="author" xlink:type="simple"><name name-style="western"><surname>W.</surname><given-names>M. Abdellah</given-names></name><xref ref-type="aff" rid="aff1"><sub>1</sub></xref></contrib></contrib-group><aff id="aff1"><label>1</label><addr-line>Radiation Protection Department, Nuclear and Radiological Regulatory Authority, Cairo, Egypt</addr-line></aff><pub-date pub-type="epub"><day>05</day><month>06</month><year>2019</year></pub-date><volume>09</volume><issue>02</issue><fpage>30</fpage><lpage>41</lpage><history><date date-type="received"><day>6,</day>	<month>April</month>	<year>2019</year></date><date date-type="rev-recd"><day>2,</day>	<month>June</month>	<year>2019</year>	</date><date date-type="accepted"><day>5,</day>	<month>June</month>	<year>2019</year></date></history><permissions><copyright-statement>&#169; Copyright  2014 by authors and Scientific Research Publishing Inc. </copyright-statement><copyright-year>2014</copyright-year><license><license-p>This work is licensed under the Creative Commons Attribution International License (CC BY). http://creativecommons.org/licenses/by/4.0/</license-p></license></permissions><abstract><p>
 
 
  
    The streambed sediments of the Suez Canal have been analyzed for determining the natural radionuclides and long-lived radionuclides such as uranium by gamma and alpha spectrometric techniques. The specific activities of 
   <sup>238</sup>U series, 
   <sup>232</sup>Th series and 
   <sup>40</sup>K (Bq/kg) were measured by gamma spectrometry based on Hyper-Pure Germanium detector (HPGe). The average specific activities of 
   <sup>226</sup>Ra(
   <sup>238</sup>U) series, 
   <sup>232</sup>Th series and 
   <sup>40</sup>K were ranged from 3.04 &#177; 1.10 to 14.70 &#177; 1.24 Bq/kg, from 1.12 &#177; 0.66 to 16.10 &#177; 1.30 and from 77 &#177; 4.90 to 350.50 &#177; 8.90 Bq/kg respectively. The concentration of 
   <sup>238</sup>U and 
   <sup>234</sup>U in the streambed sediments are ranged from 3.24 &#177; 0.21 to 13.34 &#177; 0.61 ppm and from 3.18 &#177; 0.02 to 13.77 &#177; 0.03 ppm in dry weight respectively. 
   <sup>234</sup>U/
   <sup>238</sup>U ratios of the sediments are relatively lower than unity in many locations indicating the preferential uranium leaching process. The results with the high ratios for 
   <sup>234</sup>U/
   <sup>238</sup>U were observed in the sediment collected from Port Said. This may be attributed to the sorption of uranium by sediment which has a relatively high content of organic matter. The geochemical behavior of sediment, the chemistry of uranium and the flow rates of water are considered as the most important factors controlling uranium isotopic composition of the streambed sediment. The result of radioactivity in sediment samples can be used to distinguish any future changes due to non-nuclear industries on the Suez Canal area. 
  
 
</p></abstract><kwd-group><kwd>Sediment</kwd><kwd> Uranium</kwd><kwd> Isotopic Ratios</kwd><kwd> Natural Radioactivity</kwd><kwd> Suez Canal</kwd><kwd> Egypt</kwd></kwd-group></article-meta></front><body><sec id="s1"><title>1. Introduction</title><p>Suez Canal is the shortest international passage for marine shipping with mass transportation of petrochemicals, crude oil, and fertilizers or radioactive materials. It passes through an area of considerable industrial, agricultural and tourist activities in which heavy metals may be released into the marine environment. The heaviest metals and radioactive isotopes have toxic effects on living organisms when exceeding a certain concentration [<xref ref-type="bibr" rid="scirp.92891-ref1">1</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref2">2</xref>] . Transportation of radioactive materials is directly associated with the progress in every activity involving the use of nuclear energy, including education, medicine, industry, research, nuclear fuel cycle, and power generation. Increasing number and quantities of radioactive material in many different forms are being transported throughout the world which results in increased public concern about radiation safety in transport. There is a considerable amount of international trade transported in Egypt through the Suez Canal and this trade also involves the transportation of radioactive materials [<xref ref-type="bibr" rid="scirp.92891-ref3">3</xref>] . El-Tahawy et al. (1994) [<xref ref-type="bibr" rid="scirp.92891-ref4">4</xref>] , measured the radioactivity levels of both natural and artificial radionuclides in the stream water of Suez Canal and related bottom sediments and found that the fate of released radionuclides would strongly depend on the chemical affinity to particulate matter in suspended loads and bottom sediments.</p><p>Over the past 20 years, much progress has been made in the understanding of the marine geochemistry of U, particularly regarding the pathways of removal from the ocean via precipitation in chemically reducing sediments. Pore-water depletion of U and sediment enrichment of U over detrital background levels by 1 to 10 &#181;g/g have been observed in a number of anoxic basins [<xref ref-type="bibr" rid="scirp.92891-ref5">5</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref6">6</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref7">7</xref>] .</p><p>γ-Spectrometry is a useful non-destructive method that permits the simultaneous determination of many radionuclides in a bulk sample, without the need for radiochemical separation. However, it is limited by the weak emission probabilities of many potentially useful emission lines, the poor efficiency of HPGe detectors over a wide energy range, the difficult task of precisely calibrating the efficiency of the detector, and the need to evaluate self-absorption and summation factors [<xref ref-type="bibr" rid="scirp.92891-ref8">8</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref9">9</xref>] .</p><p>α-Spectrometry, with a detection limit often 100 - 1000 times lower than γ-spectrometry, is a very sensitive alternative technique. The efficiency of α-particle detection depends only on geometric factors and, when a careful radiochemical separation process is carried out, it does not suffer from spectral interference. However, the overall process is time-consuming and impractical for large-scale screening of environmental samples. Thus, α-spectrometry is used only for very specific aspects of environmental radioactivity surveys, in particular for uranium and plutonium determination [<xref ref-type="bibr" rid="scirp.92891-ref8">8</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref9">9</xref>] .</p><p>Diffusion of U (VI) from bottom water into sediments, followed by reduction to U (IV), which is precipitated or adsorbed to sediment solids, is regarded as the primary source of authigenic Uranium in these sediments. There is no doubt that authigenic Uranium formation in suboxic and anoxic sediments is the most important mechanism removing Uranium from ocean water, accounting for 40% to 70% of the riverine Uranium input flux [<xref ref-type="bibr" rid="scirp.92891-ref10">10</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref11">11</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref12">12</xref>] . Uranium concentrations and activity ratios have been studied in several environmental systems: ice-sheets (Koide and Goldberg, 1983) [<xref ref-type="bibr" rid="scirp.92891-ref13">13</xref>] , soils (Greeman and Rose, 1990) [<xref ref-type="bibr" rid="scirp.92891-ref14">14</xref>] , oceanic sediments (Barnes and Cochran, 1990) [<xref ref-type="bibr" rid="scirp.92891-ref15">15</xref>] , groundwater (Copenhaver et al., 1992) [<xref ref-type="bibr" rid="scirp.92891-ref16">16</xref>] , surface waters (Sarin et al., 1990) [<xref ref-type="bibr" rid="scirp.92891-ref17">17</xref>] , etc. They have provided important information about the behavior of these radionuclides in the environment.</p><p>In this paper, the author describe a method, kept as simple as possible, for the determination of uranium content from sediment samples in addition to the comparison between the activity concentrations determined by gamma and alpha spectrometer.</p><p>The aim of the present work is the evaluation of the radiological baseline of the most important locations along the Suez Canal for the update and establishing the radiological map of that area. The work is extended to determine uranium concentrations and the isotopic ratios between <sup>234</sup>U and <sup>238</sup>U after radiochemical separation to clarify any potential variation of natural uranium in the sediment.</p></sec><sec id="s2"><title>2. Materials and Methods</title><sec id="s2_1"><title>2.1. Sample Collection</title><p>Thirty marine sediment samples were collected from six mains locations along the canal, each sample about 1 kg was placed in a plastic bag and transported to the environmental laboratory. The collected samples were prepared for gamma counting by drying at 105˚C, crushed, homogenized and sieved through 200 mesh sieve shakers. A volume of 100 cm<sup>3</sup> from the sample is transferred to a polyethylene container. The samples were collected from the heavy industrial locations on the long line of the Suez Canal starting from Athmanon coast (WA1) at the south of the canal followed by El-Ismailia port (WA2), El-Salam bridge (WA3), El-Qantara (WA4), Port Said (WA5) and Port Faud (WA6) in the north as depicted in <xref ref-type="fig" rid="fig1">Figure 1</xref> [<xref ref-type="bibr" rid="scirp.92891-ref18">18</xref>] . The samples were sealed with silicon and stored for one month to ensure the secular equilibrium between parent and daughter isotopes in the nuclear chain, then measured by the Hyper Pure germanium detector (HPGe). The sediment samples from the locations under this investigation were analyzed by alpha spectrometry for the precise determination of uranium and the isotopic ratios between <sup>234</sup>U and <sup>238</sup>U.</p></sec><sec id="s2_2"><title>2.2. Gamma Spectrometric Measurement</title><p>The activity measurements have been performed by gamma ray spectrometer at Nuclear and Radiological Regulatory Authority using vertical HPGe detector of a relative efficiency about 40% and full width at half maximum (FWHM) of 1.95 keV for <sup>60</sup>Co gamma energy line at 1.33 MeV. The detector was operated with Canberra Genie 2000 software for gamma acquisition and analysis system supported by the LabSOCS (Laboratory Source less Calibration Software) [<xref ref-type="bibr" rid="scirp.92891-ref19">19</xref>] . The HPGe detector was contained in about 10 cm thickness free standing lead castle providing a low background environment, to shield the detector from lead fluorescent X-rays and bremsstrahlung. The lead was lined with 1.5 mm iron and</p><p>1.0 mm Cu metals. Before performing the spectroscopic measurements, the spectrometer has been verified by using multi-nuclides standard sources distributed in the same geometry and a reference materials soil number (IAEA-326) which have certified concentration of natural radioactivity provided by the IAEA.</p><p><sup>238</sup>U cannot be measured directly from gamma ray spectrometry as it possesses only a feeble gamma line 49.55 keV of very low emission probability (0.064%). <sup>238</sup>U activity is usually estimated from gamma lines of radon daughters assuming secular equilibrium among its daughter radionuclides. This assumption holds good, only under undisturbed conditions, where there is a natural secular equilibrium between <sup>238</sup>U and <sup>226</sup>Ra. Under oxidizing conditions, where uranium mostly stays in hexavalent states is more susceptible to leaching than radium. In such case, direct gamma line 63.29 keV of <sup>234</sup>Th, is the most suitable gamma energy to determine <sup>238</sup>U by gamma ray spectrometry [<xref ref-type="bibr" rid="scirp.92891-ref20">20</xref>] . However, thorium is highly insoluble of nature and therefore in case of disequilibrium between <sup>224</sup>Ra and thoron (<sup>220</sup>Rn) daughters. Thorium concentrations cannot be measured from gamma lines of thoron daughters. In this case, two prominent gamma energies of <sup>228</sup>Ac, the third member in the series, 338 keV (11.3%) and 911 keV (25.8%) are usually being used to estimate the parent thorium [<xref ref-type="bibr" rid="scirp.92891-ref21">21</xref>] . So, the specific activity calculations of <sup>238</sup>U and <sup>232</sup>Th series were obtained indirectly from the gamma rays emitted by their progenies assuming the secular equilibrium while <sup>40</sup>K activities were determined from the 1460.7 keV gamma line.</p></sec><sec id="s2_3"><title>2.3. Alpha Spectrometric Measurement</title><p>1 gram from each sediment samples was ground until mesh size between 50 and 100 mesh, then digested by microwave model Mars CEM using 4 ml conc. HNO<sub>3</sub> and 4 ml HCl in the tube contained the sample and applying pressure 160 Psi and temperature 190˚C. The samples took outside the instrument when the pressure reached 50 psi and a temperature less than 50˚C. Finally, the samples treated with 4 ml of HF to destroy the silica followed by evaporation to dryness for loss the excess of hydrofluoric acid. The residues were dissolved in 9 MHCl followed by filtration and applying the radiochemical separation (<xref ref-type="fig" rid="fig2">Figure 2</xref>) that was studied and validated by the investigators Juhani (2001) [<xref ref-type="bibr" rid="scirp.92891-ref22">22</xref>] and Jukka et al. (2010) [<xref ref-type="bibr" rid="scirp.92891-ref23">23</xref>] .</p><p>The activity concentration of uranium isotopes is determined according to the Equation (1):</p><p>A Nuclide = N Nuclide − N Background m &#215; t &#215; Y Tracer &#215; e f f (1)</p><p>Where: N<sub>Nuclide</sub> is the count from the studied nuclide, N<sub>Background</sub> is the background count, t is the counting time (s), m is the mass of the sample (kg) and eff is the efficiency of the detector (%).</p><p>Quality assurance policies were followed for the methods by analyzing several environmental reference samples, e.g. IAEA-326, Dl-1a Canadian reference ore and blank samples. Alpha spectrometers, employing PIPS detectors with efficiencies ranged from 17% to 25% and an average resolution of 17 keV in <sup>241</sup>Am alphas, and connected up to a computerized multi-channel analyzer operating with maestro software (ORTEC). The samples were measured for not less than 60,000 s. The Minimum Detectable Activity (MDA), determined for the detection system and radiochemical procedures adopted in this study as presented by Equation (2) Currie, 1968 [<xref ref-type="bibr" rid="scirp.92891-ref24">24</xref>] .</p><p>MDA = 2.71 + 3.29 N p k ∗ V ∗ t [ Bq / cpm ] (2)</p><p>Where: N<sub>p</sub> is the background (CPM), k is the calibration factor (CPM/Bq) and m is the mass of the sample (kg). The calibration factor was defined according to Equation (3)</p><p>k = N t ∗ A (3)</p><p>Where: t is the counting time of the sample (s), A is the activity of the standard (Bq), and N is the number of counts from the standard sample. The MDA was 0.17 mBq for samples with counting time 1600-minute and chemical recovery ranged between 75% - 80%.</p></sec></sec><sec id="s3"><title>3. Results and Discussions</title><p>The specific activity concentrations in the collected sediment samples for the radionuclides, <sup>226</sup>Ra (<sup>238</sup>U), <sup>232</sup>Th series and <sup>40</sup>K are determined by gamma spectrometry and presented in <xref ref-type="table" rid="table1">Table 1</xref>. The obtained results showed that <sup>226</sup>Ra (<sup>238</sup>U) activities concentration ranged from 5.00 &#177; 1.25 to 13.91 &#177; 1.18 Bq/kg with an average of 8.34 &#177; 1.44 while <sup>232</sup>Th series from 2.5 &#177; 0.90 to 15.30 &#177; 1.23 with an average of 7.39 &#177; 1.11 and <sup>40</sup>K from 90.70 &#177; 6.30 to 332.9 &#177; 8.45 with an average of 205.10 &#177; 8.04 Bq/kg, these values are in agreement with the results obtained by other authors Waleed et al. in 2015 [<xref ref-type="bibr" rid="scirp.92891-ref25">25</xref>] and El Mamoney and Khater in 2004 [<xref ref-type="bibr" rid="scirp.92891-ref26">26</xref>] .</p><p>The determined results for <sup>226</sup>Ra(<sup>238</sup>U) ,<sup>232</sup>Th and <sup>40</sup>K are lower than the international average for the radioactivity levels which are 35, 50 and 500 Bq/kg respectively as reported in UNSCEAR, 2000 [<xref ref-type="bibr" rid="scirp.92891-ref27">27</xref>] . The relatively high content of uranium series <sup>226</sup>Ra (<sup>238</sup>U) at Port Said (WA5) and Port Faud (WA6) locations</p><table-wrap id="table1" ><label><xref ref-type="table" rid="table1">Table 1</xref></label><caption><title> The average specific activity (Bq/kg) of <sup>226</sup>Ra(<sup>238</sup>U), <sup>232</sup>Th and <sup>40</sup>K in sediment samples using γ-Spectroscopy</title></caption><table><tbody><thead><tr><th align="center" valign="middle" >Sample locations</th><th align="center" valign="middle" ><sup>226</sup>Ra(<sup>238</sup>U) (Bq/kg)</th><th align="center" valign="middle" ><sup>232</sup>Th (Bq/kg)<sup> </sup></th><th align="center" valign="middle" ><sup>40</sup>K (Bq/kg)<sup> </sup></th></tr></thead><tr><td align="center" valign="middle" >Athmanon Coast (WA1)</td><td align="center" valign="middle" >5.00 &#177; 1.25</td><td align="center" valign="middle" >2.50 &#177; 0.90</td><td align="center" valign="middle" >95.77 &#177; 5.10</td></tr><tr><td align="center" valign="middle" >Ismailia Port (WA2)</td><td align="center" valign="middle" >6.11 &#177; 1.20</td><td align="center" valign="middle" >2.90 &#177; 0.8</td><td align="center" valign="middle" >290.60 &#177; 8.90</td></tr><tr><td align="center" valign="middle" >El-Salam Bridge (WA3)</td><td align="center" valign="middle" >5.50 &#177; 1.23</td><td align="center" valign="middle" >6.33 &#177; 0.85</td><td align="center" valign="middle" >89.67 &#177; 6.10</td></tr><tr><td align="center" valign="middle" >El-Qantara (WA4)</td><td align="center" valign="middle" >7.12 &#177; 2.40</td><td align="center" valign="middle" >4.50 &#177; 1.02</td><td align="center" valign="middle" >90.70 &#177; 6.30</td></tr><tr><td align="center" valign="middle" >Port Said (WA5)</td><td align="center" valign="middle" >13.05 &#177; 1.40</td><td align="center" valign="middle" >12.80 &#177; 1.90</td><td align="center" valign="middle" >330.90 &#177; 13.70</td></tr><tr><td align="center" valign="middle" >Port Faud (WA6)</td><td align="center" valign="middle" >13.91 &#177; 1.18</td><td align="center" valign="middle" >15.30 &#177; 1.23</td><td align="center" valign="middle" >332.97 &#177; 8.45</td></tr><tr><td align="center" valign="middle" >Average</td><td align="center" valign="middle" >8.45 &#177; 1.44</td><td align="center" valign="middle" >7.39 &#177; 1.11</td><td align="center" valign="middle" >205.10 &#177; 8.09</td></tr></tbody></table></table-wrap><p>may be attributed to the release of uranium through the wastewater contaminated with TE-NORM in the production of oil and gas industries. In addition, the high content of carbonate can increase the leaching of uranium with the formation of soluble carbonate complex. The geological nature in some locations may contain a reasonable content of uranium and that be easily leached to the water [<xref ref-type="bibr" rid="scirp.92891-ref25">25</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref26">26</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref27">27</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref28">28</xref>] . In general, the average activity concentrations of U in the area under this investigation are close to the reported values 20 - 50 Bq/kg for uncontaminated sediments (UNSCEAR, 1988) [<xref ref-type="bibr" rid="scirp.92891-ref29">29</xref>] .</p><p>The Radium equivalent (Ra<sub>eq</sub>) has been calculated according to UNSCARE in 1994 [<xref ref-type="bibr" rid="scirp.92891-ref29">29</xref>] , moreover the highest Ra<sub>eq</sub> value reached 61.42 &#177; 3.58 Bq/kg in Port Faud (WA6) sediments, while the lower value amounted 15.95 &#177; 2.93 Bq/kg in Athmanon sediment (WA1). All the samples have radium equivalent lower than the limit set by the OECD (The Organization for Economic Cooperation and Development) report (370 Bq/kg) [<xref ref-type="bibr" rid="scirp.92891-ref30">30</xref>] . It is observed that Ra<sub>eq</sub> values lower the maximum permissible radium activity (Ref. value is 370 Bq/kg) as reported by UNSCEAR, 1994 [<xref ref-type="bibr" rid="scirp.92891-ref31">31</xref>] .</p><p>The Uranium results obtained by alpha spectrometry were summarized in <xref ref-type="table" rid="table2">Table 2</xref>, where the concentration of <sup>238</sup>U ranged from 3.24 &#177; 0.21 (WA4) to 13.34 &#177; 0.61 (WA5) ppm with an average 7.22 &#177; 0.38 ppm and for <sup>234</sup>U ranged from 3.18 &#177; 0.02 (WA4) to 13.77 &#177; 0.34 (WA5) ppm with an average 6.68 &#177; 0.02 ppm and chemical recovery about 80%. The Conversion factors were used to convert Bq/kg to ppm by the equations explained by IAEA in (2003) [<xref ref-type="bibr" rid="scirp.92891-ref32">32</xref>] . The results show that <sup>234</sup>U and <sup>238</sup>U are in radiological equilibrium, namely activity ratio of <sup>234</sup>U to <sup>238</sup>U being 1.0 [<xref ref-type="bibr" rid="scirp.92891-ref33">33</xref>] , if the uranium was placed in a closed system. Isotopic fractionation of heavy elements such as uranium usually is less significant compared with that of light elements such as hydrogen and oxygen. It can be observed that the measured <sup>234</sup>U/<sup>238</sup>U values are in good agreement with the (certified/reference) values [<xref ref-type="bibr" rid="scirp.92891-ref33">33</xref>] . The obtained result reflects the accuracy of radiochemical separation of uranium isotopes by alpha spectrometry as shown in <xref ref-type="fig" rid="fig3">Figure 3</xref>.</p><table-wrap id="table2" ><label><xref ref-type="table" rid="table2">Table 2</xref></label><caption><title> Uranium concentration in ppm and the isotopic ratios between <sup>234</sup>U and <sup>238</sup>U from the studied locations</title></caption><table><tbody><thead><tr><th align="center" valign="middle" >Sample locations</th><th align="center" valign="middle" >Samples code</th><th align="center" valign="middle" ><sup>238</sup>U ppm</th><th align="center" valign="middle" ><sup>234</sup>U ppm</th><th align="center" valign="middle" ><sup>234</sup>U/<sup>238</sup>U %</th><th align="center" valign="middle" ><sup>234</sup>U/<sup>238</sup>U Ref. value [<xref ref-type="bibr" rid="scirp.92891-ref33">33</xref>]</th><th align="center" valign="middle" >Difference (Ref.-Measured.) %</th></tr></thead><tr><td align="center" valign="middle" >Athmanon Coast</td><td align="center" valign="middle" >WA1</td><td align="center" valign="middle" >6.51 &#177; 0.35</td><td align="center" valign="middle" >6.15 &#177; 0.02</td><td align="center" valign="middle" >0.95 &#177; 0.06</td><td align="center" valign="middle" >1.00</td><td align="center" valign="middle" >5</td></tr><tr><td align="center" valign="middle" >Ismailia Port</td><td align="center" valign="middle" >WA2</td><td align="center" valign="middle" >4.82 &#177; 0.26</td><td align="center" valign="middle" >3.49 &#177; 0.02</td><td align="center" valign="middle" >0.91 &#177; 0.06</td><td align="center" valign="middle" >1.00</td><td align="center" valign="middle" >9</td></tr><tr><td align="center" valign="middle" >El-Salam Bridge</td><td align="center" valign="middle" >WA3</td><td align="center" valign="middle" >4.82 &#177; 0.27</td><td align="center" valign="middle" >3.49 &#177; 0.02</td><td align="center" valign="middle" >0.91 &#177; 0.06</td><td align="center" valign="middle" >1.00</td><td align="center" valign="middle" >9</td></tr><tr><td align="center" valign="middle" >El-Qantara</td><td align="center" valign="middle" >WA4</td><td align="center" valign="middle" >3.24 &#177; 0.205</td><td align="center" valign="middle" >3.18 &#177; 0.02</td><td align="center" valign="middle" >0.98 &#177; 0.08</td><td align="center" valign="middle" >1.00</td><td align="center" valign="middle" >2</td></tr><tr><td align="center" valign="middle" >Port Said</td><td align="center" valign="middle" >WA5</td><td align="center" valign="middle" >13.34 &#177; 0.61</td><td align="center" valign="middle" >13.77 &#177; 0.03</td><td align="center" valign="middle" >1.03 &#177; 0.06</td><td align="center" valign="middle" >1.00</td><td align="center" valign="middle" >-3</td></tr><tr><td align="center" valign="middle" >Port Faud</td><td align="center" valign="middle" >WA6</td><td align="center" valign="middle" >10.59 &#177; 0.59</td><td align="center" valign="middle" >10.01 &#177; 0.03</td><td align="center" valign="middle" >0.95 &#177; 0.06</td><td align="center" valign="middle" >1.00</td><td align="center" valign="middle" >5</td></tr></tbody></table></table-wrap><p>The calculated isotopic ratios (<xref ref-type="table" rid="table2">Table 2</xref>) between <sup>234</sup>U and <sup>238</sup>U for all samples are relatively near unity and the redox regime may be expected for the corrosion of uranium isotopes from the sediment. The isotopic ratios below unity (0.9) indicating some degree of dissolution limited Uranium migration during the alternation of uranyl oxide hydrates was proposed on the basis of petrographic evidence and this may agree with Finch et al., in 1992 [<xref ref-type="bibr" rid="scirp.92891-ref34">34</xref>] . The most uranium concentration under the present work recorded their highest mean value (1.03) at North of the canal (Port Said) and this attributed to the locations at Port Said (WA5) and Port Faud (WA6) which are the most industrialized area in the north of Suez Canal. The difference between measured and reference value show a relatively small variation from −3 at (WA5) to 9 at locations (WA2 &amp; WA3).</p><p>The obtained results agreed with those studies by other investigators El-Moselhy et al. in 1998 [<xref ref-type="bibr" rid="scirp.92891-ref35">35</xref>] and Ibrahim N.M. in 1994 [<xref ref-type="bibr" rid="scirp.92891-ref36">36</xref>] who studied the pollution and uranium in the canal. The middle of the canal is affected mainly by agriculture effluents, shipyard of the Suez Canal and sewage discharge from Ismailia city. In Suez Canal, the principal process dominating the ecosystem is the mean sea level, the velocity and direction of the current which are responsible for the distribution of pollutants and radioisotopes such as uranium isotopes along Suez Canal [<xref ref-type="bibr" rid="scirp.92891-ref37">37</xref>] .</p><p>These results can be interpreted as explained by another study [<xref ref-type="bibr" rid="scirp.92891-ref38">38</xref>] about the Uranium redox-sensitive and biologically-related element, and a small change to more reduced conditions that may be immobilize the soluble U(+6) to insoluble U(+4), while more oxidizing conditions have the reverse effect. Transfer of U from water to sediments is known as arising from adsorption and/or adhesion onto settling particles including organic matter. An additional transfer of U may result from diffusion into the sediments and reduction of U(+6) to U(+4) with precipitation of U(OH)<sub>4</sub> at the redox boundary [<xref ref-type="bibr" rid="scirp.92891-ref38">38</xref>] . The most likely explanation of the relatively high <sup>234</sup>U/<sup>238</sup>U activity ratio (larger than unity) in port Said WA5 is the preferential leaching of <sup>234</sup>U due to a recoil from rocks and sediments during weathering compared with <sup>238</sup>U from solid phase, caused by radiation damage of crystal lattice upon alpha decay of <sup>238</sup>U and oxidation of insoluble tetravalent <sup>234</sup>U to soluble hexavalent <sup>234</sup>U during decay solution phase [<xref ref-type="bibr" rid="scirp.92891-ref27">27</xref>] [<xref ref-type="bibr" rid="scirp.92891-ref37">37</xref>] . Comparison between uranium activity concentration in Bq/kg dry weight, estimated by alpha and gamma spectroscopic measurements in the sediment samples show a wide variation from the equality ratios between <sup>238</sup>U and <sup>226</sup>Ra(<sup>238</sup>U) which may suggest a disturbance of equilibrium in sediment samples under the present study.</p></sec><sec id="s4"><title>4. Conclusion</title><p>The activity concentration of uranium, thorium, and potassium in sediments from different locations along the Suez Canal has been determined. The mean activity concentration of <sup>226</sup>Ra (<sup>238</sup>U), <sup>232</sup>Th and <sup>40</sup>K were 8.45 &#177; 1.44, 7.39 &#177; 1.11 and 205.10 &#177; 8.09 Bq∙kg<sup>−1</sup>, respectively. The calculated Radium equivalent values were lower than the worldwide average reported by UNSCARE in 2000 [<xref ref-type="bibr" rid="scirp.92891-ref27">27</xref>] . The data indicated a wide deviation from the equality ratio, between <sup>238</sup>U determined by alpha and <sup>226</sup>Ra (<sup>238</sup>U) measured by gamma spectrometry which suggested a disturbance for the state of equilibrium in these sediments. Such disequilibrium may be attributed to escape of radon because its gaseous nature which leads to lowering all daughter isotopes in decay series, and hence lowering <sup>228</sup>Ra (<sup>238</sup>U) values. The selective deposition of <sup>226</sup>Ra and <sup>238</sup>U depend on the solubility product in water and the chemical composition. The activity ratio for <sup>234</sup>U/<sup>238</sup>U is ranged from 0.91 &#177; 0.06 to 1.03 &#177; 0.06. The <sup>234</sup>U/<sup>238</sup>U ratios were found to be relatively close to unity with a maximum difference ~9 % between the reference value and the certified value (1). The increase in the uranium concentration in the sediment has been indicated in Port Said (WA5) and Port Faud (WA6) as a result of the progressive and intensive increase of the industrial activities. Future work will explore the correlations between total dissolved uranium activity in the Canal water and chemical, physical characteristics of the Sediment.</p></sec><sec id="s5"><title>Acknowledgements</title><p>The author very much appreciated the support provided by Helsinki University, Radiochemical Laboratory, Staff members, as well as the technical assistance from Dr. Juhani Suksi and Prof. Jukka Lehto.</p></sec><sec id="s6"><title>Conflicts of Interest</title><p>The authors declare no conflicts of interest regarding the publication of this paper.</p></sec><sec id="s7"><title>Cite this paper</title><p>Abdellah, W.M. (2019) Precise Determination of Uranium Isotopes in Suez Canal Sediment. 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