Pub Date : 2024-08-16DOI: 10.1016/j.nucana.2024.100128
Tingting Wang
The recent advancements in neutron scattering technologies in China, with the development of China's first Spin-Echo Small-Angle Neutron Scattering (SESANS) spectrometer at China Mianyang Research Reactor (CMRR) and the integration of a Very Small Angle Neutron Scattering (VSANS) instrument at China Spallation Neutron Source (CSNS), have significantly bolstered the nation's scientific capabilities. This review aims to highlight the distinctive features and applications of SESANS and SANS, and to offer a valuable contribution by demonstrating how SESANS and SANS can be leveraged for the study of soft matters and solid-state materials, with a particular emphasis on the benefits of techniques such as chain labeling, contrast variation, and contrast matching. We also aim to illustrate what types of information can be gleaned from these methods. The review is structured to first introduce the general concepts of SANS and SESANS, followed by a discussion on the information these techniques can provide. Then the applications of these techniques, in combination with other techniques, on various material investigations will be demonstrated. The review concludes with a summary and future perspectives, aiming to inspire further interdisciplinary research and collaboration, and beneficial to a broader audience.
随着中国绵阳中子研究堆(CMRR)研制出中国第一台自旋回波小角中子散射(SESANS)光谱仪,以及中国溅射中子源(CSNS)集成了甚小角中子散射(VSANS)仪器,中国中子散射技术的最新进展极大地增强了国家的科学能力。本综述旨在强调 SESANS 和 SANS 的独特功能和应用,并通过展示如何利用 SESANS 和 SANS 研究软物质和固态材料,特别强调链标记、对比度变化和对比度匹配等技术的益处,从而做出有价值的贡献。我们还旨在说明从这些方法中可以收集到哪些类型的信息。综述的结构是首先介绍 SANS 和 SESANS 的一般概念,然后讨论这些技术可以提供的信息。然后将展示这些技术与其他技术相结合在各种材料研究中的应用。综述的最后是总结和未来展望,旨在激励进一步的跨学科研究与合作,并使更多读者受益。
{"title":"Structural insights into soft matter materials via spin echo small angle neutron scattering and small angle neutron scattering","authors":"Tingting Wang","doi":"10.1016/j.nucana.2024.100128","DOIUrl":"10.1016/j.nucana.2024.100128","url":null,"abstract":"<div><p>The recent advancements in neutron scattering technologies in China, with the development of China's first Spin-Echo Small-Angle Neutron Scattering (SESANS) spectrometer at China Mianyang Research Reactor (CMRR) and the integration of a Very Small Angle Neutron Scattering (VSANS) instrument at China Spallation Neutron Source (CSNS), have significantly bolstered the nation's scientific capabilities. This review aims to highlight the distinctive features and applications of SESANS and SANS, and to offer a valuable contribution by demonstrating how SESANS and SANS can be leveraged for the study of soft matters and solid-state materials, with a particular emphasis on the benefits of techniques such as chain labeling, contrast variation, and contrast matching. We also aim to illustrate what types of information can be gleaned from these methods. The review is structured to first introduce the general concepts of SANS and SESANS, followed by a discussion on the information these techniques can provide. Then the applications of these techniques, in combination with other techniques, on various material investigations will be demonstrated. The review concludes with a summary and future perspectives, aiming to inspire further interdisciplinary research and collaboration, and beneficial to a broader audience.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 3","pages":"Article 100128"},"PeriodicalIF":0.0,"publicationDate":"2024-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000284/pdfft?md5=35c8e99ee7a1b6e9645a922724fdd3ac&pid=1-s2.0-S2773183924000284-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142040717","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}
Pub Date : 2024-08-13DOI: 10.1016/j.nucana.2024.100126
Adil Bardane , Nabil Maalej , El Mahjoub Chakir , El Mehdi Al Ibrahmi
This study uses Monte Carlo simulations to examine the dose enhancement effect of gold nanoparticles (AuNPs) in radiation therapy and its effects on DNA damage. Using the GATE- 9.0 and Geant4-DNA packages, Monte Carlo simulations were used to simulate a mathematical phantom and determine the energy deposition in the vicinity of AuNP. The simulations were conducted for various photon beam energies (50, 100, 250, and 6000 keV) with and without the presence of different-size AuNPs (10, 30, 50 and 100 nm). The dose enhancement factor (DER) was evaluated using Geant4-DNA to examine the effects AuNP sizes and photon beam energies on DNA damage. A multi-scale Monte Carlo simulation was conducted to evaluate enhanced DNA damage owing to nanoparticles in the proximity of cancer cells. The Monte Carlo simulations indicated that AuNPs boost the dose delivery, resulting in enhanced energy deposition and subsequent DNA damage. The DER analysis revealed a significant increase in the dose deposition within DNA, leading to single or double-strand breaks. Geant4-DNA simulations revealed information on the dosage enhancement factor for various AuNP sizes and photon beam intensities, enabling a deeper comprehension of the underlying mechanics. The outcomes of this study emphasize the potential of AuNPs as effective radiosensitizers in radiation therapy and contribute to the growing body of research on the use of nanotechnology in enhancing cancer treatment outcomes. Further investigations and experimental validations are necessary to optimize the usage of AuNPs for improved radiation therapy.
{"title":"Gold nanoparticle effect on dose and DNA damage enhancement in the vicinity of gold nanoparticles","authors":"Adil Bardane , Nabil Maalej , El Mahjoub Chakir , El Mehdi Al Ibrahmi","doi":"10.1016/j.nucana.2024.100126","DOIUrl":"10.1016/j.nucana.2024.100126","url":null,"abstract":"<div><p>This study uses Monte Carlo simulations to examine the dose enhancement effect of gold nanoparticles (AuNPs) in radiation therapy and its effects on DNA damage. Using the GATE- 9.0 and Geant4-DNA packages, Monte Carlo simulations were used to simulate a mathematical phantom and determine the energy deposition in the vicinity of AuNP. The simulations were conducted for various photon beam energies (50, 100, 250, and 6000 keV) with and without the presence of different-size AuNPs (10, 30, 50 and 100 nm). The dose enhancement factor (DER) was evaluated using Geant4-DNA to examine the effects AuNP sizes and photon beam energies on DNA damage. A multi-scale Monte Carlo simulation was conducted to evaluate enhanced DNA damage owing to nanoparticles in the proximity of cancer cells. The Monte Carlo simulations indicated that AuNPs boost the dose delivery, resulting in enhanced energy deposition and subsequent DNA damage. The DER analysis revealed a significant increase in the dose deposition within DNA, leading to single or double-strand breaks. Geant4-DNA simulations revealed information on the dosage enhancement factor for various AuNP sizes and photon beam intensities, enabling a deeper comprehension of the underlying mechanics. The outcomes of this study emphasize the potential of AuNPs as effective radiosensitizers in radiation therapy and contribute to the growing body of research on the use of nanotechnology in enhancing cancer treatment outcomes. Further investigations and experimental validations are necessary to optimize the usage of AuNPs for improved radiation therapy.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 4","pages":"Article 100126"},"PeriodicalIF":0.0,"publicationDate":"2024-08-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000260/pdfft?md5=28fbf1d35df9f3b5d4b49c66adb0a166&pid=1-s2.0-S2773183924000260-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142011368","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}
Pub Date : 2024-08-06DOI: 10.1016/j.nucana.2024.100124
H.S. Anushree , N. Sowmya , H.C Manjunatha , S. Shubha
<div><div>We conducted an in-depth investigation of Mn-induced fusion reactions aimed at synthesizing superheavy elements with atomic numbers Z=119 to Z=123. Our analysis considers the total potential, which combines Coulomb and nuclear potentials. The nuclear potential was calculated using the Thomas–Fermi approach, a valuable method for modeling the behavior of nucleons in atomic nuclei. within the framework of advanced statistical model, the evaporation residue cross-sections were determined. At optimal energies, we have calculated capture, fusion, and evaporation residue cross-sections for the reactions of all the projectile–target combinations. All <span><math><msup><mrow></mrow><mrow><mn>53</mn><mo>−</mo><mn>55</mn></mrow></msup></math></span>Mn isotopes with larger half-lives were taken into consideration as projectiles. Fusion reactions between <span><math><msup><mrow></mrow><mrow><mn>53</mn><mo>−</mo><mn>55</mn></mrow></msup></math></span>Mn projectiles with <span><math><msup><mrow></mrow><mrow><mn>238</mn><mo>−</mo><mn>242</mn><mo>,</mo><mn>244</mn></mrow></msup></math></span>Pu, <span><math><msup><mrow></mrow><mrow><mn>241</mn><mo>−</mo><mn>243</mn></mrow></msup></math></span>Am, <span><math><msup><mrow></mrow><mrow><mn>242</mn><mo>−</mo><mn>248</mn><mo>,</mo><mn>250</mn></mrow></msup></math></span>Cm, <span><math><msup><mrow></mrow><mrow><mn>247</mn><mo>−</mo><mn>249</mn></mrow></msup></math></span>Bk, and <span><math><msup><mrow></mrow><mrow><mn>248</mn><mo>−</mo><mn>254</mn></mrow></msup></math></span>Cf. Detailed investigations were made and promising reactions viz. <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Pu</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>293</sup>119, <span><math><mrow><msup><mrow></mrow><mrow><mn>242</mn></mrow></msup><mi>Am</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>294</sup>120, <span><math><mrow><msup><mrow></mrow><mrow><mn>247</mn></mrow></msup><mi>Cm</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>299</sup>121, <span><math><mrow><msup><mrow></mrow><mrow><mn>248</mn></mrow></msup><mi>Bk</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>300</sup>122 and <span><math><mrow><msup><mrow></mrow><mrow><mn>251</mn></mrow></msup><mi>Cf</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>53</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>301</sup>123 with maximum <span><math><msub><mrow><mi>σ</mi></mrow><mrow><mi>E</mi><mi>R</mi></mrow></msub></math></span> are found to be 415.1 fb at 240 MeV, 115.4 fb at 244 MeV, 36.5 fb at 245 MeV, 13.6 fb at 249 MeV, 5.4 fb at 250 MeV for Z=119-123 respectively. Th
{"title":"Fusion mechanism involved in the synthesis of superheavy element Z>118 using Mn projectiles","authors":"H.S. Anushree , N. Sowmya , H.C Manjunatha , S. Shubha","doi":"10.1016/j.nucana.2024.100124","DOIUrl":"10.1016/j.nucana.2024.100124","url":null,"abstract":"<div><div>We conducted an in-depth investigation of Mn-induced fusion reactions aimed at synthesizing superheavy elements with atomic numbers Z=119 to Z=123. Our analysis considers the total potential, which combines Coulomb and nuclear potentials. The nuclear potential was calculated using the Thomas–Fermi approach, a valuable method for modeling the behavior of nucleons in atomic nuclei. within the framework of advanced statistical model, the evaporation residue cross-sections were determined. At optimal energies, we have calculated capture, fusion, and evaporation residue cross-sections for the reactions of all the projectile–target combinations. All <span><math><msup><mrow></mrow><mrow><mn>53</mn><mo>−</mo><mn>55</mn></mrow></msup></math></span>Mn isotopes with larger half-lives were taken into consideration as projectiles. Fusion reactions between <span><math><msup><mrow></mrow><mrow><mn>53</mn><mo>−</mo><mn>55</mn></mrow></msup></math></span>Mn projectiles with <span><math><msup><mrow></mrow><mrow><mn>238</mn><mo>−</mo><mn>242</mn><mo>,</mo><mn>244</mn></mrow></msup></math></span>Pu, <span><math><msup><mrow></mrow><mrow><mn>241</mn><mo>−</mo><mn>243</mn></mrow></msup></math></span>Am, <span><math><msup><mrow></mrow><mrow><mn>242</mn><mo>−</mo><mn>248</mn><mo>,</mo><mn>250</mn></mrow></msup></math></span>Cm, <span><math><msup><mrow></mrow><mrow><mn>247</mn><mo>−</mo><mn>249</mn></mrow></msup></math></span>Bk, and <span><math><msup><mrow></mrow><mrow><mn>248</mn><mo>−</mo><mn>254</mn></mrow></msup></math></span>Cf. Detailed investigations were made and promising reactions viz. <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Pu</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>293</sup>119, <span><math><mrow><msup><mrow></mrow><mrow><mn>242</mn></mrow></msup><mi>Am</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>294</sup>120, <span><math><mrow><msup><mrow></mrow><mrow><mn>247</mn></mrow></msup><mi>Cm</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>299</sup>121, <span><math><mrow><msup><mrow></mrow><mrow><mn>248</mn></mrow></msup><mi>Bk</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>55</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>300</sup>122 and <span><math><mrow><msup><mrow></mrow><mrow><mn>251</mn></mrow></msup><mi>Cf</mi></mrow></math></span> (<span><math><mrow><msup><mrow></mrow><mrow><mn>53</mn></mrow></msup><mi>Mn</mi></mrow></math></span>, 3n)<sup>301</sup>123 with maximum <span><math><msub><mrow><mi>σ</mi></mrow><mrow><mi>E</mi><mi>R</mi></mrow></msub></math></span> are found to be 415.1 fb at 240 MeV, 115.4 fb at 244 MeV, 36.5 fb at 245 MeV, 13.6 fb at 249 MeV, 5.4 fb at 250 MeV for Z=119-123 respectively. Th","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 4","pages":"Article 100124"},"PeriodicalIF":0.0,"publicationDate":"2024-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142327640","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}
The objective of this study is to assess natural activity in soil to estimate potential radiological risks for the population. Given that soil is inherently radioactive and can reach hazardous levels, it is crucial to determine the activities of radionuclides such as Potassium-40 and Uranium-238 descendants at different depths and geographical positions. For this work, gamma spectrometry method was employed to analyze soil samples collected at three different positions in the Missour region. Each position was sampled at five different depths, spaced 5 cm apart, resulting in a total of 15 samples. The activity of Potassium-40 and Uranium238 descendants in the soil was accurately assessed using Lvis software, enabling the estimation of radiological doses.
{"title":"Evaluation of Potassium-40 and Uranium-238 activities and radiological risk in Missour, Morocco soils using gamma spectrometry","authors":"Abdessamad Didi , Hamid Bounouira , Abir Adnane , Soumaia El Khamsi Chahd , Hamid Amsil , Abdelwahab Badague , Iliasse Aarab","doi":"10.1016/j.nucana.2024.100125","DOIUrl":"10.1016/j.nucana.2024.100125","url":null,"abstract":"<div><p>The objective of this study is to assess natural activity in soil to estimate potential radiological risks for the population. Given that soil is inherently radioactive and can reach hazardous levels, it is crucial to determine the activities of radionuclides such as Potassium-40 and Uranium-238 descendants at different depths and geographical positions. For this work, gamma spectrometry method was employed to analyze soil samples collected at three different positions in the Missour region. Each position was sampled at five different depths, spaced 5 cm apart, resulting in a total of 15 samples. The activity of Potassium-40 and Uranium238 descendants in the soil was accurately assessed using Lvis software, enabling the estimation of radiological doses.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 3","pages":"Article 100125"},"PeriodicalIF":0.0,"publicationDate":"2024-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000259/pdfft?md5=b064fa8f6785305a19ec020d1f7ebcfe&pid=1-s2.0-S2773183924000259-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141964342","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}
Pub Date : 2024-07-31DOI: 10.1016/j.nucana.2024.100123
Reddi Rani L. , N. Sowmya , H.C. Manjunatha , M.M. Armstrong Arasu
The role of entrance channel parameters such as , charge asymmetry , mass-asymmetry (), charge product (), mean fissility , Coulomb interaction parameter and on compound nucleus formation of actinide nuclei using heavy ion fusion reactions were investigated. For the formation of compound nuclei, the considered atomic number range of the projectile varies between and the mass number lies between . Similarly, the studied target atomic number varies between and the mass number range is . Among these entrance channel parameters, is more systematic for , and . In addition to entrance channel parameters, the and also play a significant role in the prediction of . The proposed empirical formulae are applicable to the compound nuclei from Fr to Sg. These findings are significant for the prediction from Fr to Sg.
{"title":"Compound nucleus formation probability of heavy and superheavy nuclei synthesized using heavy ion fusion reactions","authors":"Reddi Rani L. , N. Sowmya , H.C. Manjunatha , M.M. Armstrong Arasu","doi":"10.1016/j.nucana.2024.100123","DOIUrl":"10.1016/j.nucana.2024.100123","url":null,"abstract":"<div><div>The role of entrance channel parameters such as <span><math><mrow><msup><mrow><mi>Z</mi></mrow><mrow><mn>2</mn></mrow></msup><mo>/</mo><mi>A</mi></mrow></math></span>, charge asymmetry <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>z</mi></mrow></msub></math></span>, mass-asymmetry (<span><math><msub><mrow><mi>η</mi></mrow><mrow><mi>A</mi></mrow></msub></math></span>), charge product (<span><math><mrow><msub><mrow><mi>Z</mi></mrow><mrow><mn>1</mn></mrow></msub><msub><mrow><mi>Z</mi></mrow><mrow><mn>2</mn></mrow></msub></mrow></math></span>), mean fissility <span><math><msub><mrow><mi>χ</mi></mrow><mrow><mi>m</mi></mrow></msub></math></span>, Coulomb interaction parameter and <span><math><mrow><mrow><mo>(</mo><mi>N</mi><mo>−</mo><mi>Z</mi><mo>)</mo></mrow><mo>/</mo><mrow><mo>(</mo><mi>N</mi><mo>+</mo><mi>Z</mi><mo>)</mo></mrow></mrow></math></span> on compound nucleus formation of actinide nuclei using heavy ion fusion reactions were investigated. For the formation of compound nuclei, the considered atomic number range of the projectile varies between <span><math><mrow><mn>5</mn><mo>≤</mo><mi>Z</mi><mo>≤</mo><mn>14</mn></mrow></math></span> and the mass number lies between <span><math><mrow><mn>10</mn><mo>≤</mo><mi>A</mi><mo>≤</mo><mn>34</mn></mrow></math></span>. Similarly, the studied target atomic number varies between <span><math><mrow><mn>78</mn><mo>≤</mo><mi>Z</mi><mo>≤</mo><mn>92</mn></mrow></math></span> and the mass number range is <span><math><mrow><mn>197</mn><mo>≤</mo><mi>A</mi><mo>≤</mo><mn>238</mn></mrow></math></span>. Among these entrance channel parameters, <span><math><msub><mrow><mi>P</mi></mrow><mrow><mi>C</mi><mi>N</mi></mrow></msub></math></span> is more systematic for <span><math><mfrac><mrow><mrow><mo>(</mo><mi>N</mi><mo>−</mo><mi>Z</mi><mo>)</mo></mrow></mrow><mrow><mrow><mo>(</mo><mi>N</mi><mo>+</mo><mi>Z</mi><mo>)</mo></mrow></mrow></mfrac></math></span>, <span><math><mrow><msup><mrow><mi>Z</mi></mrow><mrow><mn>2</mn></mrow></msup><mo>/</mo><mi>A</mi></mrow></math></span> and <span><math><msub><mrow><mi>α</mi></mrow><mrow><mi>z</mi></mrow></msub></math></span>. In addition to entrance channel parameters, the <span><math><msub><mrow><mi>E</mi></mrow><mrow><mi>c</mi><mi>m</mi></mrow></msub></math></span> and <span><math><msub><mrow><mi>E</mi></mrow><mrow><mi>B</mi><mi>a</mi><mi>s</mi><mi>s</mi></mrow></msub></math></span> also play a significant role in the prediction of <span><math><msub><mrow><mi>P</mi></mrow><mrow><mi>C</mi><mi>N</mi></mrow></msub></math></span>. The proposed empirical formulae are applicable to the compound nuclei from Fr to Sg. These findings are significant for the <span><math><msub><mrow><mi>P</mi></mrow><mrow><mi>C</mi><mi>N</mi></mrow></msub></math></span> prediction from Fr to Sg.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 4","pages":"Article 100123"},"PeriodicalIF":0.0,"publicationDate":"2024-07-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142358342","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}
Pub Date : 2024-07-20DOI: 10.1016/j.nucana.2024.100122
Long Qiu , Jinsong Zhang , Tu Lan , Jiali Liao , Yuanyou Yang , Feize Li , Ning Liu
With a suitable half-life and abundant radiolabeling strategy, 225Ac has become one of the most promising radionuclides in the area of targeted alpha therapy. However, limited radionuclide supply is threatening the development of 225Ac related endoradiotherapy dramatically. As the parent nuclide of 225Ac, 229Th can be produced via 226Ra(3n, 2β)229Th reaction in a nuclear reactor. However, related practice has not been conducted in large scale, since the nuclear reaction pathway for producing 229Th is complicated. In this work, the feasibility of producing 225Ac/229Th in a reactor was confirmed by systematic theoretical calculations, and a procedure that combines irradiation with separation process was proposed. The results show that 176 MBq of 229Th can be produced by irradiating 1.0 g of 226Ra with a neutron flux density of 1 × 1015 n cm−2 s−1 for 90 days. This will generate 150 MBq of 225Ac monthly from a radionuclide generator, which is sufficient for the single treatment cycle of 200 patients each year considering the radioactivity loss in radiochemical separation, transfer and radiolabeling process. In addition, this irradiation process will also produce 37.8 GBq 227Ac for the preparation of 227Ac-227Th-223Ra generator. In general, the production of 225Ac by neutron irradiation of 226Ra in reactor is practicable and holds potential to alleviate the shortage of current supply of 225Ac.
{"title":"Feasibility of producing 225Ac via thermal neutron irradiation of 226Ra: A systematic theoretical study","authors":"Long Qiu , Jinsong Zhang , Tu Lan , Jiali Liao , Yuanyou Yang , Feize Li , Ning Liu","doi":"10.1016/j.nucana.2024.100122","DOIUrl":"10.1016/j.nucana.2024.100122","url":null,"abstract":"<div><p>With a suitable half-life and abundant radiolabeling strategy, <sup>225</sup>Ac has become one of the most promising radionuclides in the area of targeted alpha therapy. However, limited radionuclide supply is threatening the development of <sup>225</sup>Ac related endoradiotherapy dramatically. As the parent nuclide of <sup>225</sup>Ac, <sup>229</sup>Th can be produced via <sup>226</sup>Ra(3n, 2β)<sup>229</sup>Th reaction in a nuclear reactor. However, related practice has not been conducted in large scale, since the nuclear reaction pathway for producing <sup>229</sup>Th is complicated. In this work, the feasibility of producing <sup>225</sup>Ac/<sup>229</sup>Th in a reactor was confirmed by systematic theoretical calculations, and a procedure that combines irradiation with separation process was proposed. The results show that 176 MBq of <sup>229</sup>Th can be produced by irradiating 1.0 g of <sup>226</sup>Ra with a neutron flux density of 1 × 10<sup>15</sup> n cm<sup>−2</sup> s<sup>−1</sup> for 90 days. This will generate 150 MBq of <sup>225</sup>Ac monthly from a radionuclide generator, which is sufficient for the single treatment cycle of 200 patients each year considering the radioactivity loss in radiochemical separation, transfer and radiolabeling process. In addition, this irradiation process will also produce 37.8 GBq <sup>227</sup>Ac for the preparation of <sup>227</sup>Ac-<sup>227</sup>Th-<sup>223</sup>Ra generator. In general, the production of <sup>225</sup>Ac by neutron irradiation of <sup>226</sup>Ra in reactor is practicable and holds potential to alleviate the shortage of current supply of <sup>225</sup>Ac.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 3","pages":"Article 100122"},"PeriodicalIF":0.0,"publicationDate":"2024-07-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000223/pdfft?md5=459ab0fb9ccb924e8ab5a6fed4199880&pid=1-s2.0-S2773183924000223-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141839148","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}
Pub Date : 2024-07-16DOI: 10.1016/j.nucana.2024.100121
Oghenevovwero Emmanuel Esi
Well water quality has been characterized with constant and continuous changes via the interaction of rock, soil and natural nano-filters which terminates at the aquiferous layer for clean well-water collection. The continuous exploration and production of crude oil has resulted significant increase of unwanted elements such as naturally occurring radionuclides in the water-bed which necessitates this study. The study determines the radionuclides based health impact or hazards associated with drinking water from crude oil exploration/production release in Ughievwen and Udu communities of Delta State, Nigeria. Sixty well water samples (three samples from each community) were collected and analyzed using sodium iodide (Nal (Tl)) detector. The obtained mean values of 238U, 232Th and 40K are 6.91 1.62BqL−1, 4.39 1.47 BqL−1 and 24.54 1.59 BqL−1 respectively. The 238U, 232Th and 40K results showed that the measured values are higher than the world standard (UNSCEAR; WHO) and the control values The mean values of total annual effective dose of different age groups are: 11.08 mSvy−1, 2.54 mSvy−1, 1.93 mSvy−1, 2.52 mSvy−1, 7.03 mSvy−1 and 1.12 mSvy−1 respectively. While the mean committed effective dose of adult is 55.94 mSvy−1. The total annual effective dose, committed effective dose, cancer risks and hereditary effects are all lower than recommended limit (WHO; ICRP; USEPA) and reported scientific values except 11.08 mSvy−1 and 7.03 mSvy−1 that are higher than limit. It is evident from obtained results that the drinking water may not be radiologically safe for use by the public, which necessitates routine monitoring and caution to circumvent increase in radiation and the radiological of the studied communities’ drinking water. This is to avoid long term radiological risk arising from accumulation of such release in the studied communities.
{"title":"Radiological impact of hydrocarbon waste release on drinking water of ughievwen and udu communities, delta state Nigeria","authors":"Oghenevovwero Emmanuel Esi","doi":"10.1016/j.nucana.2024.100121","DOIUrl":"10.1016/j.nucana.2024.100121","url":null,"abstract":"<div><p>Well water quality has been characterized with constant and continuous changes via the interaction of rock, soil and natural nano-filters which terminates at the aquiferous layer for clean well-water collection. The continuous exploration and production of crude oil has resulted significant increase of unwanted elements such as naturally occurring radionuclides in the water-bed which necessitates this study. The study determines the radionuclides based health impact or hazards associated with drinking water from crude oil exploration/production release in Ughievwen and Udu communities of Delta State, Nigeria. Sixty well water samples (three samples from each community) were collected and analyzed using sodium iodide (Nal (Tl)) detector. The obtained mean values of <sup>238</sup>U, <sup>232</sup>Th and <sup>40</sup>K are 6.91 <span><math><mrow><mo>±</mo></mrow></math></span> 1.62BqL<sup>−1</sup>, 4.39 <span><math><mrow><mo>±</mo></mrow></math></span> 1.47 BqL<sup>−1</sup> and 24.54 <span><math><mrow><mo>±</mo></mrow></math></span> 1.59 BqL<sup>−1</sup> respectively. The <sup>238</sup>U, <sup>232</sup>Th and <sup>40</sup>K results showed that the measured values are higher than the world standard (UNSCEAR; WHO) and the control values The mean values of total annual effective dose of different age groups are: 11.08 mSvy<sup>−1</sup>, 2.54 mSvy<sup>−1</sup>, 1.93 mSvy<sup>−1</sup>, 2.52 mSvy<sup>−1</sup>, 7.03 mSvy<sup>−1</sup> and 1.12 mSvy<sup>−1</sup> respectively. While the mean committed effective dose of adult is 55.94 mSvy<sup>−1</sup>. The total annual effective dose, committed effective dose, cancer risks and hereditary effects are all lower than recommended limit (WHO; ICRP; USEPA) and reported scientific values except 11.08 mSvy<sup>−1</sup> and 7.03 mSvy<sup>−1</sup> that are higher than limit. It is evident from obtained results that the drinking water may not be radiologically safe for use by the public, which necessitates routine monitoring and caution to circumvent increase in radiation and the radiological of the studied communities’ drinking water. This is to avoid long term radiological risk arising from accumulation of such release in the studied communities.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 3","pages":"Article 100121"},"PeriodicalIF":0.0,"publicationDate":"2024-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000211/pdfft?md5=869ab386a09f2b2eca91c3c05f0eb686&pid=1-s2.0-S2773183924000211-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141850667","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}
This article examines the impact of temperature on the steel collimator cap and the primary beam shutter. These components will be used to implement the Prompt Gamma Activation Analysis (PGAA) technique in the Moroccan TRIGA Mark-II research reactor. The steel collimator plug is essential for forming the neutron beam, while the main role of the shutter is to stop the beam when the channel is inactive. This study analyzes the effect of temperature on the collimator and shutter system, particularly focusing on the variation in maximum temperature over a month of operation with 8-h cycles per day, the behavior of temperature over 24 h, the total heat flux as a function of the length of the experimental device, the temperature distribution in mild steel (E235) and 304L stainless steel materials, and the total displacement and strain gradient as a function of temperature. All calculations were performed using COMSOL Multiphysics simulation software, based on the finite element method.
{"title":"Temperature distribution in the PGAA system: Collimator, shutter, and filter in TRIGA Mark II reactor","authors":"Jamila Yousfi , Abdessamad Didi , Hamane Lemziouka , Lamiae Mrharrab , Hamid Amsil , Otman Jai , Hamid Bounouira , Khalid Larakil","doi":"10.1016/j.nucana.2024.100120","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100120","url":null,"abstract":"<div><p>This article examines the impact of temperature on the steel collimator cap and the primary beam shutter. These components will be used to implement the Prompt Gamma Activation Analysis (PGAA) technique in the Moroccan TRIGA Mark-II research reactor. The steel collimator plug is essential for forming the neutron beam, while the main role of the shutter is to stop the beam when the channel is inactive. This study analyzes the effect of temperature on the collimator and shutter system, particularly focusing on the variation in maximum temperature over a month of operation with 8-h cycles per day, the behavior of temperature over 24 h, the total heat flux as a function of the length of the experimental device, the temperature distribution in mild steel (E235) and 304L stainless steel materials, and the total displacement and strain gradient as a function of temperature. All calculations were performed using COMSOL Multiphysics simulation software, based on the finite element method.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 3","pages":"Article 100120"},"PeriodicalIF":0.0,"publicationDate":"2024-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S277318392400020X/pdfft?md5=ed234df0ea998ce112ebc55e0b3b6931&pid=1-s2.0-S277318392400020X-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141607678","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}
This study investigates the critical significance of anode material selection in defining the energy spectrum and properties of X-ray photons in medical physics applications. Using the GATE platform and Monte Carlo simulations, a direct relationship between anode material atomic number and photon fluence is demonstrated. As the atomic number increases from Z = 29 (Copper) to Z = 74 (Tungsten), photon fluence rises by 62 %, indicating a substantial impact on X-ray production. Furthermore, the X-ray spectrum is affected by this material-driven changes, revealing a noticeable shift towards higher energy values: the mean energy of the continuous spectrum rises from 46.97 keV for Copper to 49.0 keV for Tungsten. The thermal properties of the material affect the temperature increase at the focal point. Rhodium and Molybdenum have a higher temperature rise than Copper (Cu) and Tungsten (W), because Cu and W have a greater thermal diffusion compared to other materials. These findings underscore the significance of anode material choice in optimizing X-ray systems which may enhance diagnostic accuracy and efficiency in diverse applications.
本研究探讨了阳极材料的选择在确定医学物理应用中 X 射线光子的能谱和特性方面的重要意义。利用 GATE 平台和蒙特卡罗模拟,证明了阳极材料原子序数与光子通量之间的直接关系。当原子序数从 Z = 29(铜)增加到 Z = 74(钨)时,光子通量增加了 62%,表明这对 X 射线的产生有重大影响。此外,X 射线光谱也受到这种材料驱动变化的影响,显示出向高能量值的明显转变:连续光谱的平均能量从铜的 46.97 keV 上升到钨的 49.0 keV。材料的热特性会影响焦点处的温度升高。铑和钼的温升比铜(Cu)和钨(W)高,因为与其他材料相比,铜和钨的热扩散能力更强。这些发现强调了选择阳极材料对优化 X 射线系统的重要意义,可提高各种应用中的诊断准确性和效率。
{"title":"Exploring the impact of anode material on X-ray photon fluence and characteristics: A Monte Carlo simulation study","authors":"Hassan Ouhadda , Mustapha Zerfaoui , Karim Bahhous , Yassine Oulhouq , Abdessamad Didi , Abdeslem Rrhioua , Dikra Bakari","doi":"10.1016/j.nucana.2024.100112","DOIUrl":"10.1016/j.nucana.2024.100112","url":null,"abstract":"<div><p>This study investigates the critical significance of anode material selection in defining the energy spectrum and properties of X-ray photons in medical physics applications. Using the GATE platform and Monte Carlo simulations, a direct relationship between anode material atomic number and photon fluence is demonstrated. As the atomic number increases from Z = 29 (Copper) to Z = 74 (Tungsten), photon fluence rises by 62 %, indicating a substantial impact on X-ray production. Furthermore, the X-ray spectrum is affected by this material-driven changes, revealing a noticeable shift towards higher energy values: the mean energy of the continuous spectrum rises from 46.97 keV for Copper to 49.0 keV for Tungsten. The thermal properties of the material affect the temperature increase at the focal point. Rhodium and Molybdenum have a higher temperature rise than Copper (Cu) and Tungsten (W), because Cu and W have a greater thermal diffusion compared to other materials. These findings underscore the significance of anode material choice in optimizing X-ray systems which may enhance diagnostic accuracy and efficiency in diverse applications.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 2","pages":"Article 100112"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000120/pdfft?md5=9a7db82a57fbdb3212adfe5d2e27cfe0&pid=1-s2.0-S2773183924000120-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141139792","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}
Pub Date : 2024-06-01DOI: 10.1016/j.nucana.2024.100113
Walid Oueslati
This study delves into the thermal dynamics induced by an electron beam sourced from the CIRCE III accelerator, focusing on a lead target previously employed at the National Centre for Nuclear Science and Technology (CNSTN) in Tunisia for neutron and photon production. Leveraging FLUKA software, we simulate the intricate interplay between electrons and the target surface, analyzing variations in deposited energy across different target thicknesses. Beyond elucidating the electron-target interaction, our investigation extends to predicting crucial parameters such as the maximum operational threshold and surface temperature distribution of the target. To achieve this, a computational model harnessing the finite volume method is employed, offering insights into the thermal response dynamics and paving the way for optimized operational protocols and target design refinements. Through this comprehensive analysis, we aim to advance the understanding of thermal phenomena in electron-target interactions, thereby bolstering the efficiency and safety of particle accelerator operations in diverse scientific applications.
本研究深入探讨了来自 CIRCE III 加速器的电子束所引起的热动力学,重点是突尼斯国家核科学技术中心(CNSTN)以前用于中子和光子生产的铅靶。利用 FLUKA 软件,我们模拟了电子与靶表面之间错综复杂的相互作用,分析了不同靶厚度下沉积能量的变化。除了阐明电子与靶的相互作用外,我们的研究还扩展到预测靶的最大运行阈值和表面温度分布等关键参数。为此,我们采用了一个利用有限体积法的计算模型,以深入了解热响应动力学,为优化操作规程和改进靶设计铺平道路。通过这项综合分析,我们旨在推进对电子-靶相互作用中热现象的理解,从而提高粒子加速器在各种科学应用中的运行效率和安全性。
{"title":"Simulating the impact of electron beam energy deposition on lead target temperature","authors":"Walid Oueslati","doi":"10.1016/j.nucana.2024.100113","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100113","url":null,"abstract":"<div><p>This study delves into the thermal dynamics induced by an electron beam sourced from the CIRCE III accelerator, focusing on a lead target previously employed at the National Centre for Nuclear Science and Technology (CNSTN) in Tunisia for neutron and photon production. Leveraging FLUKA software, we simulate the intricate interplay between electrons and the target surface, analyzing variations in deposited energy across different target thicknesses. Beyond elucidating the electron-target interaction, our investigation extends to predicting crucial parameters such as the maximum operational threshold and surface temperature distribution of the target. To achieve this, a computational model harnessing the finite volume method is employed, offering insights into the thermal response dynamics and paving the way for optimized operational protocols and target design refinements. Through this comprehensive analysis, we aim to advance the understanding of thermal phenomena in electron-target interactions, thereby bolstering the efficiency and safety of particle accelerator operations in diverse scientific applications.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 2","pages":"Article 100113"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000132/pdfft?md5=649bffd1aa4b7288312b8b309793fef4&pid=1-s2.0-S2773183924000132-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141324561","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}