核科学与技术国际期刊(英文)最新文献_第2页

Study of Radiological Practices in Côte d’Ivoire: Case of the Frontal Chest Examination Côte科特迪瓦放射学实践研究:胸部正面检查一例

核科学与技术国际期刊(英文) Pub Date : 2021-07-01 DOI: 10.4236/wjnst.2021.113010

I. Konaté, Djagoury Koudou

引用次数: 0

Radiological Concentration Distribution of 134Cs and 137Cs Due to a Hypothetical Accident of TRIGA Research Reactor TRIGA研究堆假想事故引起的134Cs和137Cs辐射浓度分布

核科学与技术国际期刊(英文) Pub Date : 2021-07-01 DOI: 10.4236/wjnst.2021.113009

Arif Jahan Sarawer, M. Hoq, M. A. Khae, Mahobul Islam, M. M. Rahman, M. T. Chowdhury, M. M. Rahman

{"title":"Radiological Concentration Distribution of 134Cs and 137Cs Due to a Hypothetical Accident of TRIGA Research Reactor","authors":"Arif Jahan Sarawer, M. Hoq, M. A. Khae, Mahobul Islam, M. M. Rahman, M. T. Chowdhury, M. M. Rahman","doi":"10.4236/wjnst.2021.113009","DOIUrl":"https://doi.org/10.4236/wjnst.2021.113009","url":null,"abstract":"The assessment of the radiological concentration of 134Cs and 137Cs owing to hypothetical accident of TRIGA Mark-II research Reactor at AERE, Savar, Bangladesh is presented here in this work. The concentration of 134Cs and 137Cs was estimated in different pathways consisting of the ingestion of plants, milk, and meat. The highest air concentration has been determined at 65 m distance from the core of the reactor. The maximum concentration passed off without delay simply after the accident in various directions. Local meteorological information such as average wind velocity and wind frequency were analyzed. Considering all directions, the highest concentration has been observed in the “S” direction. The concentrations of 134Cs and 137Cs were determined in ground, vegetation, milk and meat. The concentration of 137Cs is investigated to be higher than the 134Cs. The concentration of 134Cs and 137Cs was found to be lower in vegetation, milk, and meat than that of ground concentration. Overall, in this study, the concentration in meat has been investigated to be lower. In case of a reactor accident, the concentration assessment due to the ingestion of vegetables, milk, and meat will be a valuable guide for insuring radiological protection across the research reactor at AERE, Savar, Bangladesh.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49293954","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}

引用次数: 0

Determination of Element Levels of Lagoon from Townships near Cocody City Abidjan Côte D’Ivoire Using Energy Dispersive X-Ray Fluorescence 利用能量色散x射线荧光法测定阿比让科科迪市Côte科特迪瓦附近城镇泻湖中的元素含量

核科学与技术国际期刊(英文) Pub Date : 2021-04-12 DOI: 10.4236/WJNST.2021.112008

A. Agbo, K. Djagouri, J. Brigui, Konin Pierre-Claver Kakou

引用次数: 1

Modeling of Radon and Its Short-Lived Decay Products during Showering: Dose to Adult Members of the Public 阵雨期间氡及其短命衰变产物的建模：对成年公众的剂量

核科学与技术国际期刊(英文) Pub Date : 2021-04-01 DOI: 10.4236/WJNST.2021.112006

R. Rabi, L. Oufni, Khamiss Cheikh, El-Houcine Youssoufi, H. Badry, Y. Errami

引用次数: 2

Study on Helium Bubble Coalescence in Titanium with Dislocations 位错钛中氦泡聚结的研究

核科学与技术国际期刊(英文) Pub Date : 2021-04-01 DOI: 10.4236/WJNST.2021.112005

Baoling Zhang, Xue Su, Chongyang Li, Junwei Zhang

引用次数: 0

Study of Annealing the Damaged HPGe Detector 受损HPGe探测器的退火研究

核科学与技术国际期刊(英文) Pub Date : 2021-04-01 DOI: 10.4236/WJNST.2021.112007

Jianyong Zhang, X. Mo, Xiao Cai

引用次数: 0

Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT 用SERPENT模拟医用放射性同位素在快速钍循环ADS中的生产

核科学与技术国际期刊(英文) Pub Date : 2021-01-29 DOI: 10.4236/WJNST.2021.111003

Ranjana Nath-M

{"title":"Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT","authors":"Ranjana Nath-M","doi":"10.4236/WJNST.2021.111003","DOIUrl":"https://doi.org/10.4236/WJNST.2021.111003","url":null,"abstract":"Radiopharmaceuticals are used in nuclear medicine for diagnostic or therapeutic acts. The short decay half-lives of medical radioisotopes, especially those used for diagnostics, imply that they should be produced continuously and transported as quickly as possible to the medical units where they are used. Neutron-rich medical radioisotopes are generally produced in research reactors, like technetium-99m, lutetium-177, holmium-166 and iodine-131. On the other hand, proton-rich radioisotopes are produced via reactions with charged particles from accelerators like fluorine-18, gallium-67, iodine-123 and thallium-201. Beside this, innovative nuclear reactors are advocated as solutions to the issues of nuclear waste production and proliferation threats. Fast neutron, thorium-cycle and accelerator-driven subcritical (ADS) reactors are some of the most promising of them, proposed as safer fuel breeders and “waste burners”. This article examines the use of a fast thorium-cycle ADS with liquid lead-bismuth eutectic coolant for the production of molybdenum-99/technetium-99m and lutetium-177. Burnup simulation has been made with the Monte-Carlo (MC) code SERPENT. It is demonstrated that MC codes can advantageously be used to determine the optimal irradiation time for a given radioisotope in a realistic reactor core. It is also shown that fast thorium-cycle ADS is an economical option for the production of medical radioisotopes.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-01-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41734063","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}

引用次数: 0

Criticality Search of an Accelerator Driven System Using the ANET Code 利用ANET程序搜索加速器驱动系统的临界性

核科学与技术国际期刊(英文) Pub Date : 2021-01-08 DOI: 10.4236/WJNST.2021.111004

Xenofontos Thalia, Savva Panayiota, M. Varvayanni, J. Maillard, J. Silva, N. Catsaros

{"title":"Criticality Search of an Accelerator Driven System Using the ANET Code","authors":"Xenofontos Thalia, Savva Panayiota, M. Varvayanni, J. Maillard, J. Silva, N. Catsaros","doi":"10.4236/WJNST.2021.111004","DOIUrl":"https://doi.org/10.4236/WJNST.2021.111004","url":null,"abstract":"One of the most important safety parameters taken into consideration during the design and actual operation of a nuclear reactor is its control rods adjustment to reach criticality. Concerning the conventional nuclear systems, the specification of their rods’ position through the utilization of neutronics codes, deterministic or stochastic, is considered nowadays trivial. However, innovative nuclear reactor concepts such as the Accelerator Driven Systems require sophisticated simulation capabilities of the stochastic neutronics codes since they combine high energy physics, for the spallation-produced neutrons, with classical nuclear technology. ANET (Advanced Neutronics with Evolution and Thermal hydraulic feedback) is an under development stochastic neutronics code, able to cover the broad neutron energy spectrum involved in ADS systems and therefore capable of simulating conventional and hybrid nuclear reactors and calculating important reactor parameters. In this work, ANETS’s reliability to calculate the effective multiplication factor for three core configurations containing control rods of the Kyoto University Critical Assembly, an operating ADS, is examined. The ANET results successfully compare with results produced by well-established stochastic codes such as MCNP6.1.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-01-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41260249","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}

引用次数: 1

Recovery of Rare Earth Elements Present in Mining Tails, by Leaching with Nitric and Hydrochloric Solutions 硝酸和盐酸浸出法回收尾矿中的稀土元素

核科学与技术国际期刊(英文) Pub Date : 2021-01-08 DOI: 10.4236/WJNST.2021.111001

P. Fleming, Pedro Orrego, F. Pinilla

{"title":"Recovery of Rare Earth Elements Present in Mining Tails, by Leaching with Nitric and Hydrochloric Solutions","authors":"P. Fleming, Pedro Orrego, F. Pinilla","doi":"10.4236/WJNST.2021.111001","DOIUrl":"https://doi.org/10.4236/WJNST.2021.111001","url":null,"abstract":"The rare earth elements (REE) include the group of 15 lanthanides, scandium and yttrium and have diverse applications in technological and nuclear areas. The existence of REE in massive solid mining wastes generated in leaching processes of copper minerals in the Atacama region of Chile generates the possibility of creating added value to the treatment of this type of waste and supporting the development of a circular economy, generating a useful by-product in different industries. In order to know the behavior of these elements present in the solid carrier waste, a leaching process was carried out by using two agents separately, corresponding to hydrochloric and nitric acid. The technical feasibility to recover REE from carrier tail was demonstrated, the best leaching agent for these elements being a hydrochloric solution, obtaining a maximum recovery efficiency of 64.5%, for an acid concentration: 3M, temperature: 40°C and (liquid/solid) ratio: 4. Lanthanum and cerium present the best individual recoveries compared to the other REE, with a maximum efficiency for a hydrochloric solution of 75.7% and 70.0%, respectively. The interaction of operational parameters that most influence the REE recovery corresponds to the temperature and the (liquid/solid) ratio. After 4 hours of leaching, REE recovery efficiencies remain practically constant. Acid consumptions correspond to 11 (kg HCl/ton mining tail) and 29 (kg HNO3/ton mining tail). The highest amount recovery ratios of these elements correspond to 0.355 and 0.224 (kg REE/ton mining tail), for hydrochloric and nitric solutions, respectively. These results influence the types of reagents and parameters to be studied in the following stages of the global process.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-01-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48384644","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}

引用次数: 2

Major Outcomes through Recent ROSA/LSTF Experiments and Future Plans 近期ROSA/LSTF实验的主要成果和未来计划

核科学与技术国际期刊(英文) Pub Date : 2021-01-08 DOI: 10.4236/WJNST.2021.111002

T. Takeda, Y. Wada, Y. Sibamoto

{"title":"Major Outcomes through Recent ROSA/LSTF Experiments and Future Plans","authors":"T. Takeda, Y. Wada, Y. Sibamoto","doi":"10.4236/WJNST.2021.111002","DOIUrl":"https://doi.org/10.4236/WJNST.2021.111002","url":null,"abstract":"Many experiments have been conducted on accidents and transients of pressurized water reactor (PWR) employing the rig of safety assessment/large-scale test facility (ROSA/LSTF). Recent research activities concerned with the OECD/NEA international joint projects included experimental investigation via the ROSA and ROSA-2 Projects, and counterpart testing with thermal-hydraulic integral test facilities under collaboration of the PKL-2, PKL-3, ATLAS, and ATLAS-2 Projects. Major results of the related integral effect tests (IETs) with the LSTF were reviewed to experimentally identify thermal-hydraulic phenomena involved, regarding the PWR accident sequences in accordance with the new regulatory requirements for the Japanese light-water nuclear power plants. Future separate effect test using the LSTF is planned to simulate loss of emergency core cooling system (ECCS) recirculation functions in a large-break loss-of-coolant accident (LOCA). Key results of the recent IETs utilizing the LSTF and future plans were presented relevant to multiple steam generator tube rupture accident with recovery operation, small-break LOCA with accident management measure on core exit temperature reliability, and small-break LOCA with thermal stratification under cold water injection from ECCS into cold legs. Also, main outcomes of the LSTF IETs were indicated for wide spectrum LOCA with core uncovery and anticipated transient without scram following small-break LOCA under totally failed high-pressure injection system.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-01-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46155324","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}

引用次数: 0