Nuclear science abstracts最新文献

{"title":"Evaluation of the Basic Neutronics and Thermal-Hydraulics for the Safety Evaluation of the Advanced Micro Reactor (AMR)","authors":"Wayne Arthur Boyes, Johan Slabber, Charl du Toit, Francois van Heerden","doi":"10.11648/j.ns.20230801.13","DOIUrl":"https://doi.org/10.11648/j.ns.20230801.13","url":null,"abstract":"South Africa requires safe affordable distributed base load energy, one way to achieve this is to use nuclear power integrated with renewable energy sources on a decentralized basis. This suggests the development of its own micro modular nuclear reactor, to supply energy to towns, small communities, mines and processing plants. Large Light Water Reactors (LWRs) are expensive and require a large infrastructure development. A High Temperature Reactor (HTR) called the Advanced Micro Reactor (AMR) is in the process of being developed and the design philosophy is to design for inherent safety, maximally using technology that has been developed and validated in previous HTR programs albeit in a completely different and unique configuration. The concept is based on existing knowhow and experience/expertise in South Africa during the time of the Pebble Bed Modular reactor (PBMR) project. These AMR reactors are to be factory built to obtain good quality control and rolled out to various sites. Once the reactor has reached its end of life, it would be returned to a licensed organisation for refuelling. The AMR produces 10MW of thermal power. The reactor configuration uses hexagonal graphite blocks for structural and moderator material, which are arranged to form a cylindrical core layout. The fuel assemblies are silicon carbide tubes that house coated particle fuel, immersed in a lead-bismuth eutectic alloy (LBE). Each fuel assembly is contained in a boring within the graphite moderator that allows an annulus for cooling. There are 420 fuel assemblies in the core. Low enriched fuel in the form of UO₂ or UCO is used. Helium gas is used as coolant. The coolant enters the core at 450°C and exits at 750°C. The mechanical, neutronic and thermal-hydraulic design of the AMR, is being evaluated with assistance from STL Nuclear (Pty) Ltd., the University of Pretoria (UP), the North-West University and the South African Nuclear Energy Corporation (NECSA). The OSCAR-5 code package, together with the Serpent neutronic code were used to perform the basic neutronic studies while the Flownex package was used to determine the thermal-hydraulic and safety evaluation for the Design Base Accident (DBA) specifically the Depressurized Loss of Forced Cooling (DLOFC) event.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"17 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-05-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135672917","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":"Reunderstand and Discuss the Hardness Limits of RCC-M M5110 Part Materials","authors":"Yu-sheng Shen, Fang-zhong Li, Wen-sheng Ma, Zhou Jie, Xing-ying Zhao, Li-jun Yan","doi":"10.11648/j.ns.20230801.11","DOIUrl":"https://doi.org/10.11648/j.ns.20230801.11","url":null,"abstract":": RCC-M M5110 is the procurement code for rolling or forging bars for bolts and drive rods of class 1, 2 and 3 equipment of nuclear power plants. The individual high strength steels involved in this specification specify only the minimum hardness of the material and have no limit on the maximum hardness. The material selection of major components of nuclear power machinery equipment must meet the requirements of load bearing and safe operation","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89601335","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":"Energies of Doubly Excited ^1,3P° Resonances in He-like Systems Below the N = 2–14 Hydrogenic Threshold","authors":"Jean Kouhissoré Badiane, Mamadou Diouldé Ba, A. Diallo, Momar Talla Gning","doi":"10.11648/j.ns.20220701.12","DOIUrl":"https://doi.org/10.11648/j.ns.20220701.12","url":null,"abstract":"","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"42 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74560863","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":"Structural Assessment of the European DEMO Water-Cooled Lithium Lead Breeding Blanket Central Outboard Segment Under Remote Maintenance Loading Conditions","authors":"G. Bongiovì, Pietro Alessandro Di Maio","doi":"10.11648/j.ns.20220701.11","DOIUrl":"https://doi.org/10.11648/j.ns.20220701.11","url":null,"abstract":"","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"21 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80997662","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":"Investigation of Alignment Effects of Neutron and Proton Pairs in High Spin States of Band Crossing for 159,160Sm Isotopes Using Projected Shell Model (PSM)","authors":"M. Pahlavani, Malihe Teimoori","doi":"10.11648/J.NS.20210603.11","DOIUrl":"https://doi.org/10.11648/J.NS.20210603.11","url":null,"abstract":"Energy spectrum of nucleus is one the important information for better recognition of nuclear force and interaction of nucleon inside of the nucleus. Energy levels of nucleus are measured by detecting gamma- ray energy spectrum when a target nucleus bombarded with a special projectile to excite it in to levels higher than ground state. On the other hand, there are several models to calculate nuclear energy levels. Solution of the Schrodinger equation by considering a suitable potential is direct method to obtain energy levels of a quantum mechanical system like nucleus. Projected shell model is a model of this type that is developed by solving the Schrodinger equation for a set of potentials along with role of spin. Band structure and yrast bands for even-even and odd-even isotopes of Samarium (159,160Sm) are calculated using a Fortran code founded based on the projected shell model (PSM). Energy levels of negative and positive parity bands of 159Sm and 160Sm isotopes of Samarium nucleus are obtained separately for each spin. Kinetic and dynamic moments of inertias are also calculated for these isotopes. The acquired results are compared with the experimental data. The electromagnetic reduced transition probabilities, B(M1)/B(E2) the behavior of dynamic moment of inertia J2, rotational kinetic energy and moment of inertia J1 as a function of spin have also been investigated and proper comparison is made between the calculated results and the experimental data. The alignment phenomena of neutron-proton pairs in view of the rotational movement in high spin states has also been studied with reference to band crossing.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"7 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-10-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86473444","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":"Application of Radiation Protection of Patients in Medical Diagnostic Radiology (Case of Public Hospitals, Fianarantsoa District, Haute Matsiatra Region, Madagascar)","authors":"Said Soudjay, Vololoniaina Bernardine, Ramanandraibe Marie Jeanne, Ramanantsizehena Georgette Vololona, R. Roland, Randriamora Tiana Harimalala","doi":"10.11648/J.NS.20210601.11","DOIUrl":"https://doi.org/10.11648/J.NS.20210601.11","url":null,"abstract":"To strengthen patient radiation protection and control of medical exposure, in the Haute Matsiatra region, Fianarantsoa District, Madagascar, we have carried out a study to develop a protocol for dose assessment in diagnostic radiology in order to ensure good radiological practice. In this region, no studies have ever been done in their radiology department. The patient entrance dose (De) is one of the basic dosimetric quantities for measuring the dose delivered to the patients. Therefore, to assess the patient entrance dose (De), we have chosen two hospitals such as the Andrainjato University Hospital Center (CHUA) and the Tambavao University Hospital Center (CHUT). We have chosen four most requested radilogicals examinations (Skull, Thorax, abdomen and pelvis) and we have evaluated the entrance doses of patient and we have compared the result found to the Diagnostic Reference Levels (DRL) recommended by the IAEA for each examination. We found that, the average doses delivered to the patients during their radiographic examinations, were below the reference doses recommended by the IAEA. For this comparison carried out in these two hospitals, we can be confirmed that the values obtained can be useful for the application of regulations on the patient radiation protection and the control of medical exposure in Fianarantsoa.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"274 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-03-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73379720","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":"Radiation Dose Level and Biological Effect Toward Human Being","authors":"Baye Zinabe Kebede","doi":"10.11648/j.ns.20210602.11","DOIUrl":"https://doi.org/10.11648/j.ns.20210602.11","url":null,"abstract":"","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"71 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85143675","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":"Investigation of α-induced Reaction on Copper Isotopes for Energy Range of 15-50 Mev","authors":"Baye Zinabe Kebede","doi":"10.11648/j.ns.20210602.12","DOIUrl":"https://doi.org/10.11648/j.ns.20210602.12","url":null,"abstract":"","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"16 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75108031","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":"Study of the Dispersive Contribution Effect for Neutrons Scattering by 60Cu Nucleus Using Variational Moment Approach","authors":"Molhum Ussef, A. Belal","doi":"10.11648/J.NS.20200504.11","DOIUrl":"https://doi.org/10.11648/J.NS.20200504.11","url":null,"abstract":"The variational moment approach for the neutrons scattering analysis by 60Cu nucleus within the energy range (60-80) MeV is applied to the construction of the complex single-particle mean field felt by neutrons in 60Cu, starting from negative energy values to the positive energy values. The experimental data of the scattering neutron has been analysis by using one of the methods for optical dispersion model which depending on the afferent between the real and imaginary parts and this led to a derivation decrease in determining the optical parameters from the experimental data. Also on the stripe expending of the real potential parameters from high energy to low energy to the close area of the Coulomb barrier which characterized the lack of information about the experimental data for each, using the program SPI-GINOA in order to determine the value of the volume integral for the real and imaginary parts (surface and volume). The Value of the volume integral for the real part and integrals oh \"Hartree – Fock\" was pointed and then determined the value of real part of the potential Hartree – fock potential. In addition we also has been determined the imaginary potential (two parts the surface and the volume) and studied on function of energy for all the specific pointed ingredients. The potential dispersion was determined (surface – volume) and studied their functional energy. Therefore, we determined the radius neutron optical model and also we found its energy way match close to what reveal the correctness of method of dispersive optical model at one hand, and the accuracy in the determination of optical model parameters at other hand.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"27 1","pages":"44"},"PeriodicalIF":0.0,"publicationDate":"2020-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84010587","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":"Evaluating Precise Quantity of Decommissioning Waste by Cutting Virtual 3D Models of Large Equipment","authors":"H. Seki, M. Imamura, H. Nagase","doi":"10.11648/J.NS.20200503.12","DOIUrl":"https://doi.org/10.11648/J.NS.20200503.12","url":null,"abstract":"Equipment and piping components contaminated by radioactive materials and/or containing low-level irradiated waste must be cut, segmented, and packed into waste containers. Workers need to avoid overexposure to radiation in dismantling environments, and the number of waste containers for the pieces of equipment and piping components needs to be minimized. Thus, we developed an automatic planning method for virtually cutting 3D equipment with limitations on container size, radioactivity, weight, and dose rate. Cutting sequence data was used to formulate different cutting-work procedures, generate cut objects, and calculate the exposure during disassembling work. By calculating the required cutting length and dose-rate distribution in working environments for various cutting sequences of large equipment, the developed system is expected to aid in the planning of decommissioning. To utilize systems engineering in conjunction with elemental technologies, the following problems need to be solved; both weight and volume of the waste need to be controlled so that radioactive waste for decommissioning nuclear power plants is traceable. Identifying segmented equipment from a 3D model is key to calculating the number of volumetric segmented fragments and required number of containers. To evaluate exposure and amount of waste, we developed an automatic planning method for virtually cutting 3D equipment objects given constraints. Cutting sequence data was used to formulate different cutting workflows, generate cut objects, and calculate the exposure dose from disassembling work.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"88 1","pages":"36"},"PeriodicalIF":0.0,"publicationDate":"2020-10-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81228981","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}