Nuclear Analysis最新文献

{"title":"Design of emergency solar energy system adjacent the nuclear power plant to prevent nuclear accidents and increase safety","authors":"M. Chabook,&nbsp;S. Tashakor","doi":"10.1016/j.nucana.2023.100092","DOIUrl":"10.1016/j.nucana.2023.100092","url":null,"abstract":"<div><p>Providing sufficient energy in emergency situations in nuclear power plants is of great importance due to their crucial role in improving power plant safety and eliminating disasters.</p><p>Solar power is capable of providing a secure energy source which could be used for emergency power loads. The main goal of this study is application of solar energy for providing emergency loads of the Tehran research reactor. A 100 kW solar power plant connected to the grid and 400 kWh battery pack which is capable of providing 50 kw loads for 8 h is designed. As the first priority, the plant charges the battery pack and discharges excess energy to the power grid. Therefore, the proposed scheme, in addition to increasing safety, also has economic benefits. Design procedure of the power plant was carried out using PVsyst which is international well known software for designing solar power plants and results were investigated. Economic evaluation of the project is carried out using RETSCREEN software and different schemes are evaluated. Due to the critical nature of the power loads and their sensitivity, application of this scheme for providing emergency energy loads of the Tehran research reactor is suggested. Considering the expansion of nuclear safety and the protection of the environment and humanity, we request the respected editors and reviewers of the journal to have positive opinions about the publication of the article.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 1","pages":"Article 100092"},"PeriodicalIF":0.0,"publicationDate":"2024-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183923000460/pdfft?md5=f88f18ee219edcecf362d1206256f61b&pid=1-s2.0-S2773183923000460-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138987203","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":"Determination of 58Fe/54Fe isotope ratios in Chang’E-5 lunar regolith by instrumental neutron activation analysis","authors":"Yonggang Yao,&nbsp;Caijin Xiao,&nbsp;Liang Zhao,&nbsp;Yuqing Li,&nbsp;Tianfu Li,&nbsp;Bing Guo,&nbsp;Dongfeng Chen","doi":"10.1016/j.nucana.2024.100102","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100102","url":null,"abstract":"<div><p>Traditionally, the determination of isotope ratios is analyzed by mass spectrometry (MS) method, which is usually destructive to sample (i.e., sample dissolution). Furthermore, the ⁵⁸Fe abundance (0.282%) is generally rather low relative to other Fe isotopes, therefore, ⁵⁸Fe/⁵⁴Fe results is not reported in the routine measurement for MS methods. Given the importance of investigating a possible genetic relationship between the stable isotope composition of the Moon and the Earth, here, we firstly report the isotope ratios of ⁵⁸Fe/⁵⁴Fe in the Chang’E-5 (CE-5) scooped bulk lunar sample. In this work, the ⁵⁸Fe/⁵⁴Fe ratios were analyzed by instrumental neutron activation analysis (INAA) which is essentially distinguished and a potentially complementary advantage for MS in the determination of stable isotope ratios. These data obtained for the CE-5 lunar sample were also compared with those of terrestrial sample GBW07105.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 1","pages":"Article 100102"},"PeriodicalIF":0.0,"publicationDate":"2024-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000028/pdfft?md5=2224679dedc13a1664bd7f99e28c6e47&pid=1-s2.0-S2773183924000028-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140042614","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":"The lifetime distribution of finite fission chain group around the prompt criticality","authors":"Hui Gao,&nbsp;Qilin Xie,&nbsp;Xiaoqiang Fan","doi":"10.1016/j.nucana.2023.100091","DOIUrl":"10.1016/j.nucana.2023.100091","url":null,"abstract":"<div><p>In order to describe the behavior of finite fission chains in a fission system initiated by a δ neutron source, we present the conception of the finite fission chains group (FFCG). The group is the collectivity of the fission chains initiated by plenty of neutrons at the same time. Based on the result of the solving generating function, we deduced the lifetime distribution formula of FFCG based on the point kinetics model. Finally, the formula is validated by the experiment with a single pulse neutron source in CFBR-Ⅱ.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 4","pages":"Article 100091"},"PeriodicalIF":0.0,"publicationDate":"2023-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183923000459/pdfft?md5=bb87426a60d7bbb2bce2d5b3ba8fefc7&pid=1-s2.0-S2773183923000459-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138623868","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":"Crystallization in blend of polycaprolactone and high molecular weight polyethylene oxide","authors":"Nan Tian ,&nbsp;Junwei Chen ,&nbsp;Yanping Liu","doi":"10.1016/j.nucana.2023.100090","DOIUrl":"https://doi.org/10.1016/j.nucana.2023.100090","url":null,"abstract":"<div><p>The concentration distribution in blend of polyethylene oxide (PEO)/polycaprolactone (PCL) and subsequent crystallization were investigated with differential scanning calorimetry, in-situ small angle X-ray scattering and wide angle X-ray scattering. By using PEOs with a molecular weight of 1 × 10⁶ g/mol (PEO1M) and 1 × 10⁵ g/mol (PEO100k), respectively, it is revealed that in initial blend the concentration of PEO1M in PEO-rich region is higher than that determined by miscibility. This non-equilibrium distribution induced by crystallization is maintained after melting, since slow relaxation of PEO1M hinders the redistribution process. Crystallization behavior of blend with 25 % of PEO1M at different melting temperatures was further investigated. The crystallinity shows no dependence on melting temperature, while the long period of PEO1M decreases continuously when melting temperature exceeds 140 °C. This decrease indicates more PCL chains diffuse into PEO-rich regions with increasing temperature and molten PCL chains reduce the entanglement number of PEO1M as solvent. Moreover, the periodicity of PEO1M lamellae becomes worse when crystallization proceeds faster, which is related to slower exclusion of PCL chains.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 4","pages":"Article 100090"},"PeriodicalIF":0.0,"publicationDate":"2023-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183923000447/pdfft?md5=ebf92418a54f20f601f7b514280c2161&pid=1-s2.0-S2773183923000447-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138557576","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":"A systematic study on complementary metal-oxide semiconductor technology (CMOS) and Internet of Things (IOT) for radioactive leakage detection in nuclear plant","authors":"Swayam Patel ,&nbsp;Sakshi Sutaria ,&nbsp;Rajveer Daga ,&nbsp;Manan Shah ,&nbsp;Mitul Prajapati","doi":"10.1016/j.nucana.2023.100080","DOIUrl":"https://doi.org/10.1016/j.nucana.2023.100080","url":null,"abstract":"<div><p>Although nuclear power plants produce about 20% of India's power, the risk posed by radioactive leakage is considerable. Radiation leakage detection devices must be installed in all nuclear power plants to ensure that avoidable catastrophes never occur again and that the loss of human life is prevented. A safe atmosphere for inhabitants and workers may be ensured by keeping a consistent radiation level in all applications that use radioactive material. Complementary Metal-Oxide Semiconductor technology, or CMOS, uses complementary and symmetrical MOSFETS for logic-based functions in various applications, such as analog circuits (CMOS sensors). The Internet of Things (IoT) extends the power of the Internet beyond computing devices to a multitude of other things, processes, and environments. The main objective of this paper is to find a better and more creative solution for radioactive leakage detection techniques over present-day techniques. In this paper, the Authors aim to integrate CMOS and IOT applications for radioactive leakage detection methods on an industrial level. Within this paper, we have given brief descriptions of CMOS and IoT with their types, functions, methodology, and applications. CMOS is considered to be the most sophisticated and precise technology that can be employed to measure radiation leaks of all types (alpha rays, beta rays, gamma rays, and neutrons). With the help of IOT, massive disasters can be averted using complex alert systems. A well-coordinated combination of the two technologies has the potential to vastly increase leak detection potential and consistency. The study's major goal is to develop new and improved technology for detecting released radiation in the industry in order to obtain real-time information about the material leaked, as well as the location of the leak and the quantity of leakage that occurred, in order to reduce the danger of a natural catastrophe.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 3","pages":"Article 100080"},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49699925","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermodynamics of Thorium(IV) complexes with N-methylethylenediamine-N,Nʹ,Nʹ-triacetate in aqueous solutions: Potentiometry and microcalorimetry","authors":"Zhuoxi Li ,&nbsp;Yuyu Liang ,&nbsp;Xiang Li ,&nbsp;Wanjun Mu ,&nbsp;Baihua Chen ,&nbsp;Jun Tu ,&nbsp;Lina Lv ,&nbsp;Yanqiu Yang ,&nbsp;Xingliang Li","doi":"10.1016/j.nucana.2023.100082","DOIUrl":"10.1016/j.nucana.2023.100082","url":null,"abstract":"<div><p>The thermodynamic parameters of the complexes of Th with <em>N</em>-methylethylenediamine-<em>N</em>,<em>Nʹ</em>,<em>N</em>ʹ-triacetic acid (MEDTA; denoted as H₃L with three dissociable protons) were studied. Potentiometry and microcalorimetry were used to determine formation constants and enthalpies, respectively. Thermodynamic analysis revealed two successively formed complexes, namely, ThL⁺ and ThL₂²⁻ (L³⁻ denotes the totally deprotonated MEDTA). Results indicated that both complexation reactions were exothermic and driven by entropic force. The first stepwise reaction (Th⁴⁺ ​+ ​L³⁻ = ThL⁺) was mainly driven by entropy with minimal effect on enthalpy change. The second stepwise reaction (ThL⁺ ​+ ​L³⁻ = ThL₂²⁻) was more exothermic and showed less entropic change than the first stepwise reaction. The strong chelation of MEDTA would inhibit the hydrolysis of Th⁴⁺ and increase solubility.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 3","pages":"Article 100082"},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183923000368/pdfft?md5=c4327bb66fe3968a08c1c752b7054164&pid=1-s2.0-S2773183923000368-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135763758","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":"Computer simulation of tritium release behavior of Li4SiO4 ceramic breeder with an improved packed bed model","authors":"Guangming Ran,&nbsp;Mao Yang,&nbsp;Linjie Zhao,&nbsp;Chengjian Xiao","doi":"10.1016/j.nucana.2023.100081","DOIUrl":"https://doi.org/10.1016/j.nucana.2023.100081","url":null,"abstract":"<div><p>In order to have a deep understanding of the tritium migration and release mechanisms in ceramic breeders, computer simulation of the tritium release behavior of Li₄SiO₄ ceramic breeder was performed by using an improved tritium release model. The influences of various factors, such as surface adsorbed water, water vapor in the purge gas, hydrogen in the purge gas, grain size and tritium production amount, on the tritium release process were systematically investigated. The simulation results have shown that: 1) The surface adsorbed water and water vapor in the purge gas can remarkably facilitate tritium release as tritiated water (HTO) in low temperature region (typically &lt;450 °C); 2) Adding hydrogen to the purge gas is effective to promote tritium release as tritium gas (HT), but the effectiveness is sensitive to surface adsorbed water and water vapor in the purge gas; 3) Large grain size and tritium production amount can relatively weaken the effects of surface adsorbed water and water vapor in the purge gas. In general, the simulation results were consistent with the observations in tritium release experiments, which were helpful to further elucidate the complex behavior of tritium release from Li₄SiO₄.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 3","pages":"Article 100081"},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49699971","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"XPS determination of the uranium valences in U3O8","authors":"Ping Li ,&nbsp;Zhuanhong Lu ,&nbsp;Jingjing Wang ,&nbsp;Teng He ,&nbsp;Niya Ou ,&nbsp;Jianjun Liang ,&nbsp;Qiaohui Fan","doi":"10.1016/j.nucana.2023.100071","DOIUrl":"https://doi.org/10.1016/j.nucana.2023.100071","url":null,"abstract":"<div><p>Uranium oxides are tightly related to the whole nuclear fuel cycle in the nuclear industry. However, the understanding of the chemical states in mixed valence uranium oxides remains scattered and deserves more exploration. The current study aims to recognize the valences of uranium in U₃O₈ by a simple X-ray photoelectron spectroscopy (XPS) investigation. U₃O₈ mixed with TiO₂ was photocatalytically reduced under UV or X-ray irradiation, and the chemical states were in-situ determined by XPS. Under UV irradiation, the shoulder peaks at 380.9 eV (U 4f_7/2) and 392.7 eV (U 4f_5/2) gradually increased, and an enhancement in intensity was also observed at 399.6 eV, which is the characteristic of U(V) satellite. Therefore, it was proved that the shoulder peak originated from U(V), and U₃O₈ consists of U(V) and U(VI). Under the irradiation by X-ray, the main lines of U 4f shifted lower by ∼0.8 eV, and a new satellite at ∼397.6 eV appeared and grew with increasing irradiation time, proving the generation of U(IV). This in turn verified that the shoulder peaks in primary U₃O₈ should be U(V) rather than U(IV). Therefore, it was confirmed by the current study that there are two-U(V) and one-U(VI) in each U₃O₈ unit cell.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 2","pages":"Article 100071"},"PeriodicalIF":0.0,"publicationDate":"2023-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49699970","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Progress in measurements of fission cross sections and total cross sections at CSNS Back-n white neutron source","authors":"Rong Liu ,&nbsp;Yiwei Yang ,&nbsp;Zhizhou Ren ,&nbsp;Zhongwei Wen ,&nbsp;Jie Wen ,&nbsp;Xingyan Liu ,&nbsp;Yonghao Chen ,&nbsp;Han Yi ,&nbsp;Zijie Han ,&nbsp;Qiping Chen ,&nbsp;Jie Bao ,&nbsp;Qi An ,&nbsp;Huaiyong Bai ,&nbsp;Ping Cao ,&nbsp;Pinjing Cheng ,&nbsp;Zengqi Cui ,&nbsp;Ruirui Fan ,&nbsp;Changqing Feng ,&nbsp;Minhao Gu ,&nbsp;Fengqin Guo ,&nbsp;Peng Zhu","doi":"10.1016/j.nucana.2023.100073","DOIUrl":"https://doi.org/10.1016/j.nucana.2023.100073","url":null,"abstract":"<div><p>The neutron-induced cross sections are of great significance for the design of nuclear devices and advanced reactors for the nuclear energy production. At CSNS Back-n white neutron source, new measurements of the fission cross sections and total cross sections are performed with two sets of Day-one spectrometers based on the multi-cell fast fission ionization chamber (FIC). The neutron-induced ^236,238U fission cross sections relative to ²³⁵U from the fission threshold energy to 200 MeV were measured by using the TOF method and the Fast Ionization Chamber Spectrometer for Fission Cross Section Measurement (FIXM) in the single/double bunch mode of Back-n. The experimental uncertainties are analyzed in detail, and the results from the two modes are consistent. The measured ^236,238U/²³⁵U fission cross section ratios are compared with previous experiments and evaluations. The ^236,238U(n,f) cross sections are obtained based on the standard ²³⁵U fission cross section. The neutron total cross sections of carbon and aluminum in the energy region from 1 eV to 20 MeV have been measured by using the TOF method and transmission method based on the Neutron Total Cross Section Spectrometer (NTOX) in the double bunch mode. The total cross section results after unfolding are in good agreement with the previous measurements as well as the broadening of the ENDF/B-Ⅷ.0 evaluation with Gaussian function within the experimental uncertainty. The present results provide the experimental data for further measurements, relevant evaluations and the design of nuclear system.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 2","pages":"Article 100073"},"PeriodicalIF":0.0,"publicationDate":"2023-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49699926","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A comparative study of adsorption properties of zirconium (IV) phosphonates for removal of 90Sr","authors":"Wanjun Mu,&nbsp;Baihua Chen,&nbsp;Xingliang Li","doi":"10.1016/j.nucana.2023.100072","DOIUrl":"https://doi.org/10.1016/j.nucana.2023.100072","url":null,"abstract":"<div><p>With as goal of improving on traditional α-ZrP, four zirconium phosphonate materials were prepared as potential adsorbents for the removal of ⁹⁰Sr from nuclear wastewater. A typical sol–gel method was used, for phosphonates: hydroxy ethylidene diphosphonic acid (HEDP), amino tri-(methylenephosphonic acid) (ATMP), ethylene diamine tetra-(methylene phosphonic acid) (EDTMP), and diethylenetriamine penta-(methylenephosphonic acid) (DETPMP) to give ZrP-HEDP, ZrP-ATMP, ZrP-EDTMP and ZrP-DETPMP, respectively. These materials exhibit a similar crystalline phase to α-ZrP, but have a completely different morphology. After loading of these organophosphonate groups, the original sheet-morphology disappears, and the materials were consistent with smaller particles. However, the loading of organophosphonate groups expands the inter-layer distances. Remarkably, these materials have a stronger ability to remove Sr²⁺, with higher adsorption capacity than α-ZrP, especially ZrP-ATMP due to its wider layer distance. The maximum adsorption capacities for Sr²⁺ are 158 mg g⁻¹, 175 mg g⁻¹, 115 mg g⁻¹ and 76 mg g⁻¹for ZrP-HEDP, ZrP-ATMP, ZrP-EDTMP and ZrP-DETPMP, respectively, while that ofα-ZrP is 55 mg g⁻¹. The higher adsorption capacities of these zirconium phosphonate materials is attributed to their wider interlayer spacing, allowing more room for Sr²⁺ to move.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"2 2","pages":"Article 100072"},"PeriodicalIF":0.0,"publicationDate":"2023-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49727900","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}