Nuclear Technology & Radiation Protection最新文献_第3页

Interlaboratory comparison of radiated emission measurements using a tubular dipole 用管状偶极子测量辐射发射的实验室间比较

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2203207k

A. Kovacevic, N. Munic, Nenko Brkljač, K. Stanković

引用次数: 1

Analysis of terraforming on mars using nuclear power for the beginning of space colonization 利用核能在火星上改造地球以开始太空殖民的分析

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2203253w

T. Woo, C. Baek, K. Jang

引用次数: 0

Thermal-hydraulic analysis of light water reactors under different steady-state operating conditions, Part 1: Boiling water reactor 不同稳态工况下轻水堆的热水力分析，第1部分:沸水堆

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204259h

E. Hutli, Ramadan Kridan

{"title":"Thermal-hydraulic analysis of light water reactors under different steady-state operating conditions, Part 1: Boiling water reactor","authors":"E. Hutli, Ramadan Kridan","doi":"10.2298/ntrp2204259h","DOIUrl":"https://doi.org/10.2298/ntrp2204259h","url":null,"abstract":"The steady-state thermal-hydraulic analysis of the core of the Boiling Water Reactor (BWR/6) at nominal operating conditions is presented in this paper. The BWR/6 is produced by General Electric USA. The analysis' goal is to keep the thermal safety margin under control and the core integrity intact under steady-state operating conditions. The effects of operating conditions such as power distribution, power level, and coolant mass flow rate on the pro- posed core's performance are investigated. For this purpose, the one-dimensional computer code MITH was used. The code's reliability was tested using the General Electric benchmark 3579 MW reactor. Two-channel models were tested (the average and the hot channel). Ther- mal-hydraulic parameters such as fuel-centerline, fuel-surface, outer clad surface and coolant temperature, critical and actual local heat flux, critical and minimum critical heat flux ratio and pressure drop are evaluated along the tested channels. Temperatures, as well as actual and critical heat flux distribution profiles, were obtained. The tested operating conditions had a significant influence on these parameters, and also on the thermal-hydraulic performance. The obtained results are in good agreement with the data from the tested core. The obtained results are well within the safety margins. The good agreement between tested reactor data and MITH code calculation concerning the reactor demonstrates the reliability of the analysis methodology from a thermal-hydraulic perspective.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"290 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68549865","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Development of nuclear radiation monitors for radiation early warning systems 辐射预警系统核辐射监测仪的研制

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2203193g

V. Gostilo, A. Vlasenko, Vasily Litvinsky, Igors Krainukovs

引用次数: 0

Analysis of 238U, 226Ra, and 210Pb transfer factors from soil to the leaves of broadleaf tree species 阔叶树土壤对238U、226Ra和210Pb迁移因子分析

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2203219v

I. Vukasinovic

{"title":"Analysis of 238U, 226Ra, and 210Pb transfer factors from soil to the leaves of broadleaf tree species","authors":"I. Vukasinovic","doi":"10.2298/ntrp2203219v","DOIUrl":"https://doi.org/10.2298/ntrp2203219v","url":null,"abstract":"This analysis of 238U, 226Ra and 210Pb transfer factors from the soil to the leaves of different native broadleaf trees at sites previously modified by uranium presence and at the site of background radioactivity levels, was conducted using data from a few available studies from the literature. The broadleaf tree species Quercus ilex, Quercus suber, Eucalyptus camaldulensis, Quercus pyrenaica, Quercus ilex rotundifolia, Populus sp. and Eucalyptus botryoides Sm. at the affected sites and Tilia spp. and Aesculus hippocastanum L. at the back ground site were in cluded in the study regardless of the deciduous or evergreen origins of the leaves. In the papers cited here, data about basic soil parameters: pH, total Ca [gkg-1], sand [%], and silt + clay [%] fractions were also available. All the collected data of activity concentration [Bqkg-1] dry weight in the soil (n=14) which was in the range: 22-6606 for 238U, 38-7700 for 226Ra, and 37-7500 for 210Pb, and the tree leaves in the range: 2.7-137.6 for 238U (n=10), 2.6-134.2 for 226Ra (n=14), and 27-77.2 for 210Pb (n=14), indicated that it was normally distributed after log-transformation. The present study was conducted under the hypothesis that biological differences between the examined broadleaf tree species have a lesser influence on the transfer factors of the investigated radionuclides from soil to tree leaves compared to the impact of the soil parameters and radionuclides activity concentrations in the soil. Consequently, it was examined whether 238U, 226Ra, and 210Pb soil-to-leaves transfer factor values for average broadleaf species could be predicted statistically in the first approximation based on their activity concentration in the soil and at least one basic soil parameter using multiple linear regression.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68549147","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Thermal-hydraulic analysis of light water reactors under different steady-state operating conditions, Part 2: Pressurized water reactor 不同稳态运行条件下轻水堆的热水力分析，第2部分:压水堆

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204276h

E. Hutli, Ramadan Kridan

{"title":"Thermal-hydraulic analysis of light water reactors under different steady-state operating conditions, Part 2: Pressurized water reactor","authors":"E. Hutli, Ramadan Kridan","doi":"10.2298/ntrp2204276h","DOIUrl":"https://doi.org/10.2298/ntrp2204276h","url":null,"abstract":"The 1-D computer code MITH was used in this paper to perform sub-channel thermal-hydraulic analyses of a typical (Westinghouse model) pressurized water reactor. Two typical channels, hot and average, with the same flow rate and pressure drop, were tested under steady-state operating conditions. In this analysis, the channel with the highest temperature is designated as the hot channel. For the calculations, the channel model was divided into 20 parts. The thermal-hydraulic performance of the tested reactor was affected by power distribution, power level, and coolant mass-flow rate. Temperature distribution profiles of the fuel element and coolant are obtained for the average and hottest channels. A critical heat flux qncr analysis is also carried out and the heat fluxes in both channels were calculated. The W-3 correlation is employed to examine qncr in the hottest channel. Some data from the pressurized water reactor typical data sheet were used as input data, while others were used to validate the code. The code faithfully reproduced the Westinghouse model reactor results, including coolant, cladding, centerline, and surface fuel temperatures, quality and local heat flux qnloc, qncr and minimum departure from nucleate boiling ratio.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68549479","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor CANDU反应器中含ads富集的ThO2和废UO2燃料的可再利用性分析

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204289d

Busra Durmaz, Gizem Bakir, Bugra Arslan, H. Yapici

{"title":"Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor","authors":"Busra Durmaz, Gizem Bakir, Bugra Arslan, H. Yapici","doi":"10.2298/ntrp2204289d","DOIUrl":"https://doi.org/10.2298/ntrp2204289d","url":null,"abstract":"The study presents the analysis of the reusability of ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. The spent UO2 fuels are taken out from pressurized water reactor and CANDU spent fuels. For this analysis, the CANDU-37 reactor having a total fission thermal power of 2156 MW is considered and 14 different cases of enriched fuels taken from the previous enrichment processes are analysed by burning in this reactor. The 3-D and time-dependent critical burn up calculations are carried out by using the MCNP 2.7 code. To determine the effective burn time of each case, these calculations are performed until the values of kinf decrease to about the criticality thresh old of 1.05 for all investigated cases. The percent ages of the 239Pu and 233U fissile isotopes appear to be below weapons-grade plutonium and uranium, respectively, in all enriched fuel cases. At the end of effective burn times, the burnup values can reach the values varying in the range of 26.770 and 33.540 GWd/MTU which are a mean of 3.5-4.5 times the burnup value of the CANDU-37 reactor fed with the NatUO2 fuel. The results of this study bring out that in terms of energy production, the CANDU-37 reactor fuelled with the ThO2 and spent UO2 fuels enriched in ADS designs demonstrates higher neutronic performance than the conventional CANDU-37 reactor.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550633","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Development of direct CO2 absorption system for radiocarbon dating and bio-based carbon determination in biogenic-synthetic products 生物合成产品放射性碳定年和生物基碳测定用CO2直接吸收系统的研制

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204315s

M. Sadek, Raafat Rayan, Waleed F. Khalil

引用次数: 0

Effect of PbO incorporation with different particle size on X-ray attenuation of polystyrene 不同粒径PbO掺入对聚苯乙烯x射线衰减的影响

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2201018o

A. Osman, B. El, Samad El, Z. Alsayed, R. Awad, M. Badawi

{"title":"Effect of PbO incorporation with different particle size on X-ray attenuation of polystyrene","authors":"A. Osman, B. El, Samad El, Z. Alsayed, R. Awad, M. Badawi","doi":"10.2298/ntrp2201018o","DOIUrl":"https://doi.org/10.2298/ntrp2201018o","url":null,"abstract":"Lead oxide (PbO) bulk and nanoparticles of two different sizes (A = 78 nm and B = 54 nm) are incorporated separately into the polystyrene matrix at various concentrations (0, 10, 15, 25, and 35 %) using roll mill mixing and compressing molding techniques. The X-ray narrow-spectrum series (N-series / ISO 4037-1) is then used to investigate the radiation attenuation capability of the novel polymer composite PS/PbO, as well as the effect of varying PbO particle sizes on shielding performance. The filler dispersion and chemical elemental analysis of the synthesized composite are investigated using scanning electron microscopy and energy-dispersive X-ray spectroscopy. To determine the mass attenuation coefficients ?m, samples with various thicknesses of the synthesized composite are examined using a range of X-ray energies, and the experimental data are compared to theoretical values from NIST databases (XCOM and FFAST). The results indicate that either increasing the filler weight percentage or, decreasing the filler particle size, enhanced the attenuation parameters throughout all energies. The composite containing the smallest nanosize of PbO exhibited the maximum radiation shielding efficacy among all combinations and therefore, might be used to develop low-cost and lightweight X-ray shields.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68547460","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 3

Shielding design in neutron activation experiment system based on D-T neutron tube 基于D-T中子管的中子活化实验系统屏蔽设计

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2201042c

Jingfei Cai, Shiwei Jing, Dedong He, Yangwenting Ou, Xinyi Ling, Bingbing Li

引用次数: 0