Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2024-12-16DOI: 10.1016/j.nucana.2024.100150
Hui Gao, Meng Li
{"title":"The influence of reactor hall on the measurement of reactivity using prompt neutron method","authors":"Hui Gao, Meng Li","doi":"10.1016/j.nucana.2024.100150","DOIUrl":"10.1016/j.nucana.2024.100150","url":null,"abstract":"<div><div>In response to the phenomenon of deviation between reactivity measurement values and expected values observed in pulsed reactor experiments, the reactivity measurement process in fission pulse experiments was simulated. The phenomenon of low measurement values by the prompt neutron method has been reproduced. It was found that the return of reflected neutrons is delayed and dispersed, and some reflected neutrons did not return in time during the reactivity measurement process, resulting in low reactivity measurement values. Therefore, the measurement values obtained by the prompt neutron method need to be corrected in some cases.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100150"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143158000","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2025-01-08DOI: 10.1016/j.nucana.2025.100156
T. Krishnamoorthi , Satyanarayan Bramha , S. Chandrasekaran , R. Ravichandaran , S. Sivakumar , R. Ravisankar
{"title":"Measurement of natural radioactivity and assessment of radiological hazard indices in soil from Tirunelveli District, Tamil Nadu, India with statistical approach","authors":"T. Krishnamoorthi , Satyanarayan Bramha , S. Chandrasekaran , R. Ravichandaran , S. Sivakumar , R. Ravisankar","doi":"10.1016/j.nucana.2025.100156","DOIUrl":"10.1016/j.nucana.2025.100156","url":null,"abstract":"<div><div>The activity concentrations of naturally occurring radionuclides <sup>238</sup>U, <sup>232</sup>Th, and <sup>40</sup>K were determined in 31 soil samples collected from the Tirunelveli District of Tamil Nadu using grid sampling method. Gamma-ray spectrometry was applied using NaI(Tl) detector and a PC-based MCA. The mean radioactivity concentrations of <sup>238</sup>U, <sup>232</sup>Th, and <sup>40</sup>K were found to be 12.98 Bq.kg<sup>−1,</sup> 162.89 Bq.kg<sup>−1</sup> and 453.04 Bq.kg<sup>−1</sup>, respectively. The spatial map of the radionuclides was drawn and is discussed. The radiological hazards associated with soils were determined using radium equivalent activity (Ra<sub>eq</sub>), annual gonadal dose equivalent (AGDE), activity utilization index (AUI), internal hazard index (H<sub>in</sub>) external hazard index (H<sub>ex</sub>) and gamma representative level index (I<sub>γ</sub>), were calculated. Results were discussed and compared with the internationally recommended approved values. Statistical method was used to determine the natural associations between samples and variables. This work may provide baseline data for future soil radioactive environmental monitoring and the results of the study can serve as a reference for future radiological assessments.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100156"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642491","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2024-12-21DOI: 10.1016/j.nucana.2024.100151
T. Kiruba , P. Jayaprakash , J. Juliet Josephine Joy , J. Venkatamuthukumar , M. Suresh Gandhi , R. Ravisankar
{"title":"Assessment of metal contamination in sediment of Kerala Coast, India using EDXRF technique and Multivariate Statistical method","authors":"T. Kiruba , P. Jayaprakash , J. Juliet Josephine Joy , J. Venkatamuthukumar , M. Suresh Gandhi , R. Ravisankar","doi":"10.1016/j.nucana.2024.100151","DOIUrl":"10.1016/j.nucana.2024.100151","url":null,"abstract":"<div><div>The current study focused on the distribution of heavy metals in sediments from coastline of Kerala, India using Energy Dispersive X-ray Fluorescence (EDXRF) technique. The concentration of V, Cr, Mn, Cu, Zn, Ba, Rb, Zr, As, Br, Sr, and Pb was determined in the sediment samples. The extent of pollution to sediment was assessed via various pollution indices such as enrichment factor (EF), contamination factor (CF), geo accumulation index (I<sub>geo</sub>), metal pollution load index (MPI), degree of contamination (Cd), modified contamination degree (mCd), and potential contamination index (Cp) based on the corresponding background values. The source of origin of heavy metals and the correlation amongst the studied elements was studied using multivariate analysis approach (Pearson correlation matrix, principal component analysis and cluster analysis). The Sediment Quality Guidelines (SQGs) was applied to understand the ecotoxicological significance of heavy metal toxicity. The observed concentration of heavy metals in the studied sediments is due to anthropogenic activity and also from the discharge of municipal wastewater, domestic sewage, fishing harbor activities, industrial and aquaculture pollutants. A regular surveillance and remedial measures for contaminant discharge may reduce the metal content in the study area.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100151"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143157907","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2025-01-07DOI: 10.1016/j.nucana.2025.100155
Sylvanus Ameh Onjefu , Biere Peter Ebibuloami , Caspah Kamunda , Markus Hitila , Marius Kudumo Mutorwa , Jeya Kudi Kennedy , Euodia Hess , Damian C. Onwudiwe
{"title":"Natural radioactivity assessments and radiological hazards in agricultural soils around mining activities in Karibib, Namibia","authors":"Sylvanus Ameh Onjefu , Biere Peter Ebibuloami , Caspah Kamunda , Markus Hitila , Marius Kudumo Mutorwa , Jeya Kudi Kennedy , Euodia Hess , Damian C. Onwudiwe","doi":"10.1016/j.nucana.2025.100155","DOIUrl":"10.1016/j.nucana.2025.100155","url":null,"abstract":"<div><div>A total of 17 soil samples were randomly collected from agricultural farms around mining areas from Karibib, Erongo region, Namibia. The samples were analyzed for natural radioactivity using a high purity germanium (HPGe) detector. The average activity concentrations of <sup>226</sup>Ra, <sup>232</sup>Th and <sup>40</sup>K were 80.80, 73.60, and 493.96 Bq.kg <sup>– 1</sup> respectively. The radiological assessments were calculated in terms of radium equivalent activity (224.09 Bq.kg <sup>– 1</sup>), absorbed dose rate (102.39 nGy h-<sup>1</sup>), annual effective dose equivalent (indoor and outdoor) (1.26 mSv y <sup>– 1</sup> and 5.02 mSv y <sup>– 1</sup>) and the internal and external hazard indices (0.61) and (0.82) respectively. The average values of <sup>226</sup>Ra, <sup>232</sup>Th and <sup>40</sup>K were higher than the world average values as well as those of the radiological parameters of absorbed dose rate and annual effective dose equivalent. The average values of radium equivalent activity, and the indices radiological hazards were below the internationally acceptable limits.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100155"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642551","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2024-09-14DOI: 10.1016/j.nucana.2024.100136
Fabiola Monroy-Guzmán, Luis Escobar Alarcón
{"title":"Electrodeposition of actinides: Optimization of deposition parameters by chronoamperometric studies","authors":"Fabiola Monroy-Guzmán, Luis Escobar Alarcón","doi":"10.1016/j.nucana.2024.100136","DOIUrl":"10.1016/j.nucana.2024.100136","url":null,"abstract":"<div><div>To quantify alpha-emitting radionuclides by alpha spectrometry, it is necessary to prepare a thin and uniform alpha source on a suitable substrate. Electrodeposition is the most used electrochemical technique for this purpose. In order to better understand the electrochemical process carried out in the electrodeposition of actinides, in particular the selection of the current densities applied, a chronoamperometric study of the electrodeposition of actinides (Th, U, Pu, Am and Cm), in three different electrolytes (Na<sub>2</sub>SO<sub>4</sub>/H<sub>2</sub>SO<sub>4</sub>, NH<sub>4</sub>NO<sub>3</sub>, NaF) using stainless steel and platinum as cathode and anode, respectively, is presented. The corresponding polarization curves (potential vs. current density), characteristic for each electrolyte and actinide used, were constructed from the chronoamperometric data. The limiting diffusion current as well as the minimum current necessary for the electrodeposition process to take place were determined. To achieve a quantitative electrodeposition of actinides, a balance between OH<sup>−</sup> production and the thickness of the OH<sup>−</sup> layer formed near the cathode must be reached. These parameters are controlled by the electrolyte used and the current density applied to the electrochemical system. Actinides were electrodeposited mainly in the form of oxides, according to Raman spectroscopy results.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100136"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142527818","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2025-03-03DOI: 10.1016/j.nucana.2025.100159
Damaris Osiga-Aibangbee, Omamoke O.E. Enaroseha, Godwin K. Agbajor
{"title":"Potential health risk assessment of sediment and water in some Niger Delta areas of Nigeria","authors":"Damaris Osiga-Aibangbee, Omamoke O.E. Enaroseha, Godwin K. Agbajor","doi":"10.1016/j.nucana.2025.100159","DOIUrl":"10.1016/j.nucana.2025.100159","url":null,"abstract":"<div><div>The Niger Delta areas of Nigeria suffer substantial environmental issues owing to radionuclides pollution in sediment and water. These places are vital for local residents, supplying drinking water, food, and livelihoods. However, exposure to radionuclides causes health concerns to both people and aquatic species. This research examines health risk in sediment and water from some chosen locations in Delta State, Nigeria. Twelve (12) sediment samples and Twelve (12) water samples were randomly chosen and gathered from four communities at a depth of 10 cm, with each location giving 200 g of samples spaced of minimum of 50 m apart. Analysis was done at the CERD - IFE utilizing Gamma Ray Spectrometry, which contained a thallium-activated 16″x16″ Sodium iodide [NaI(Tl)] detector to quantify the activity concentrations of <sup>238</sup>U, <sup>232</sup>Th, and <sup>40</sup>K. The analysis indicated that activity concentrations in sediment samples for <sup>40</sup>K, <sup>238</sup>U, and, <sup>232</sup>Th varied from 294.29 ± 11.98 to 774.4 ± 10.92, 3.91 ± 0.06 to 14.13 ± 0.1, and 1.32 ± 0.05 to 5.29 ± 0.10 Bq/kg, respectively. In water samples, activity concentrations for <sup>40</sup>K, <sup>238</sup>U, and, <sup>232</sup>Th ranged from 232.32 ± 5.08 to 780.72 ± 9.31, 5.34 ± 0.06 to 11.29 ± 0.04, and 0.93 ± 0.04 to 3.07 ± 0.08 Bq/l, respectively. Base on health risk assessment, radium equivalent (Ra<sub>eq</sub>) values ranged from 242.34 to 556.41 Bq/kg, with a mean value of 396.21 Bq/kg and was found to exceed the international standard of 370 Bq/kg. The discrepancies are due to geological differences and the existence of radioactive thorium materials, variable behavior and metabolism. Although radionuclide hazard indices suggest that the communities are safe from radiation, the long-term impacts of low-dose radiation exposure might pose health problems, hence frequent monitoring of radioactive levels in sediments and water is advised.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100159"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642493","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Chemical separation of uranium-233 from neutron-irradiated 232ThO2 targets using a dual-column technique","authors":"Yu Sun, Muxiao Wu, Jijun Guo, Qingchuan Lin, Jun Tu, Xiang Xie","doi":"10.1016/j.nucana.2025.100157","DOIUrl":"10.1016/j.nucana.2025.100157","url":null,"abstract":"<div><div>Uranium-233 (<sup>233</sup>U) is an important synthetic isotope and used as isotope dilution references for safeguards, non-proliferation, and nuclear forensics measurements. In this work, the chemical separation of <sup>233</sup>U from irradiated <sup>232</sup>ThO<sub>2</sub> targets has been evaluated by a dual-column technique, where a stacked columns of Dowex 1 × 8 anion exchange resin and Dowex 50 × 8 cation exchange resin were applied. The dual-column method is simple with an overall <sup>233</sup>U recovery yield of 98 ± 1 %. The isotope purity of <sup>233</sup>U (>99 %) was confirmed and meeting the recommendations according to the quality requirements of isotope dilution mass spectrometry references.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100157"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642495","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2024-10-10DOI: 10.1016/j.nucana.2024.100140
Brahim EL Azzaoui , Ouadie Kabach , Mohamed Youssef Messous , El mahjoub Chakir , El Mehdi Alibrahmi
{"title":"Optimizing neutron shielding: A specialised container approach for Disused Sealed Radioactive Sources and orphan neutron emitters","authors":"Brahim EL Azzaoui , Ouadie Kabach , Mohamed Youssef Messous , El mahjoub Chakir , El Mehdi Alibrahmi","doi":"10.1016/j.nucana.2024.100140","DOIUrl":"10.1016/j.nucana.2024.100140","url":null,"abstract":"<div><div>Shielding Disused Sealed Radioactive Sources (DSRSs) and orphan neutron sources, such as <sup>252</sup>Cf, pose challenges due to the high penetration of neutrons, induced radioactivity in shielding materials, and the limited availability of compact, effective shielding materials. This study addresses these challenges by proposing a specialized container for the safe transport, conditioning, and disposal of neutron-emitting DSRSs and orphan sources. The computational tool that was used in this study is the Monte Carlo N-Particle (MCNP). The investigation begins with an examination of moderation materials, including high-density polyethylene (HDPE), paraffin, and water-extended polyester (WEP). Subsequently, four concrete types, namely Ordinary, Barite, Portland, and Serpentine Concrete, are scrutinized. Employing a comprehensive methodology, the design of the container is optimized to effectively moderate and absorb neutron emissions. The findings of this study demonstrate that the designed compact container can safely handle activities exceeding those studied, effectively managing up to 10 μg (about 0.2 GBq) <sup>252</sup>Cf without exceeding 25 μSv/h at the outer container contact. This suggests a promising solution for the secure management of high-activity neutron-emitting sources.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100140"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142441061","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2025-01-07DOI: 10.1016/j.nucana.2025.100154
Ahmed Abdul Hadi Mohsen , Ali Saeed jassim , Ali Abid Abojassim , Abdulhussein A. Alkufi
{"title":"Alpha emitter in samples of antibiotics commonly used in pediatric age groups","authors":"Ahmed Abdul Hadi Mohsen , Ali Saeed jassim , Ali Abid Abojassim , Abdulhussein A. Alkufi","doi":"10.1016/j.nucana.2025.100154","DOIUrl":"10.1016/j.nucana.2025.100154","url":null,"abstract":"<div><div>This investigation is aimed to assess the level of <sup>222</sup>Rn (radon-222), <sup>226</sup>Ra (radium-226), <sup>238</sup>U (uranium-238), <sup>218</sup>Po (Polonium-218), <sup>214</sup>Po (Polonium-214) in antibiotics that are commonly utilized for pediatrics in Al-Najaf, governorate. Alpha emitters were measured using a CN-85 detector. Additionally, “Annual Average Internal Effective Dose” (AAIED) and “Risk of an Excess Cancer Fatality Per Million Person” (RECFPMP) resulting from <sup>222</sup>Rn, <sup>226</sup>Ra, and <sup>238</sup>U in samples of antibiotics were assessed. The average <sup>222</sup>Rn, <sup>226</sup>Ra, and <sup>238</sup>U values were found to be 2.840, 0.173, and 2.830 Bq/kg, respectively. Moreover, the average AAIED and RECFPMP values which associated with alpha emitters assessment in all medical plant samples were 55.526 nSv/y and 0.214 × 10<sup>−6</sup>, respectively. Finally, the average levels of <sup>218</sup>Po and <sup>214</sup>Po were recorded as 15.926 and 6.716 Bq/m<sup>3</sup>, respectively. After conducting a thorough examination for the resulted data and comparing them with the globally accepted and permissible (<sup>218</sup>Po, <sup>214</sup>Po) limits, it was found that the radiation levels in samples of selected antibiotic medications prescribed for pediatrics were entirely natural and fall within the recommended range. Consequently, there is no cause for concern regarding the radioactive component of these drugs and their safe consumption by children.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100154"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642497","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear AnalysisPub Date : 2025-03-01Epub Date: 2024-10-15DOI: 10.1016/j.nucana.2024.100141
A. Arectout , H. Boukhal , M. Jarmouni , K. Laazouzi , M. Assalmi , A. Nouayti , M. Hadouachi , H. El Yaakoubi , E. Chakir
{"title":"Investigation of photon interaction parameters in Human Body Tissues using GAMOS, FLUKA, and XCOM Studies","authors":"A. Arectout , H. Boukhal , M. Jarmouni , K. Laazouzi , M. Assalmi , A. Nouayti , M. Hadouachi , H. El Yaakoubi , E. Chakir","doi":"10.1016/j.nucana.2024.100141","DOIUrl":"10.1016/j.nucana.2024.100141","url":null,"abstract":"<div><div>This study aims to evaluate different photon interaction parameters of human body organs at nine photon energies (0.021 keV–1.25 MeV) using GAMOS and FLUKA Monte Carlo codes. The Mass attenuation coefficients, Mean Free Path, Half Value Layer, Tenth Value Layer, and Mass absorption coefficients of the breast, lung, kidney, pancreas, liver, eye lens, thyroid, brain, ovary, heart, large intestine blood, skin, spleen, muscle, and cortical bone were investigated and compared against the standard values available from the tables of XCOM database. This comparison demonstrated a good agreement, with all calculated values deviating less than 6 %. In addition, the values obtained with the GAMOS code were similar to those obtained using the FLUKA code. These comparisons indicate very good agreement and revealed that both FLUKA and GAMOS codes can be used as a computational tool for determining the photon interaction parameters of any material and also different energies, whose data are not available in the literature.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100141"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142527819","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}