{"title":"Spallation reaction study to improve cross-section measurements of fission products in nuclear waste using Cs-137 on proton or deuteron ranging from 0.1 to 2.4 GeV","authors":"Abdessamad Didi, Hamid Amsil, Hamid Bounouira, Khalid Laraki, Hamid Marah, Hassane Dekhissi, Mohamed Yjjou","doi":"10.1504/ijnest.2023.132649","DOIUrl":"https://doi.org/10.1504/ijnest.2023.132649","url":null,"abstract":"","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"13 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135989612","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}
Pub Date : 2023-01-01DOI: 10.1504/ijnest.2023.10059803
M. Mustafa Azeem
{"title":"Effect of nanovoids on the displacement cascades and mechanical properties in INCOLOY-800H: A molecular dynamics study","authors":"M. Mustafa Azeem","doi":"10.1504/ijnest.2023.10059803","DOIUrl":"https://doi.org/10.1504/ijnest.2023.10059803","url":null,"abstract":"","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"11 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"136306404","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}
Pub Date : 2023-01-01DOI: 10.1504/ijnest.2023.132689
Rukia Jabar Dosh, Ali K. Hasan, Ali Abid Abojassim
{"title":"Health effect of radon gas in water on children at Al-Najaf schools","authors":"Rukia Jabar Dosh, Ali K. Hasan, Ali Abid Abojassim","doi":"10.1504/ijnest.2023.132689","DOIUrl":"https://doi.org/10.1504/ijnest.2023.132689","url":null,"abstract":"","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"241 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135987672","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}
Pub Date : 2022-12-01DOI: 10.57237/j.jest.2022.01.001
L. Xin, Zhang Jie, Donghua Gao, H. Shang, Ruitao Sun, Rongxin Li
{"title":"Experimental Investigation on the Evolution Mechanism of Deep Coal-rock Mechanical Properties Under Varying Temperature Conditions","authors":"L. Xin, Zhang Jie, Donghua Gao, H. Shang, Ruitao Sun, Rongxin Li","doi":"10.57237/j.jest.2022.01.001","DOIUrl":"https://doi.org/10.57237/j.jest.2022.01.001","url":null,"abstract":"","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"107 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76206002","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}
Pub Date : 2022-12-01DOI: 10.57237/j.jest.2022.01.002
Liu Jie, Zhou Xingyu, Min Zhongshun, L. Rui, Xie Congjiao, Li Mingxiao
{"title":"Numerical Simulation of Draining and Expanding of Gas Storage Based on Mechanism Model","authors":"Liu Jie, Zhou Xingyu, Min Zhongshun, L. Rui, Xie Congjiao, Li Mingxiao","doi":"10.57237/j.jest.2022.01.002","DOIUrl":"https://doi.org/10.57237/j.jest.2022.01.002","url":null,"abstract":"","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"69 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82194060","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}
Pub Date : 2020-12-21DOI: 10.1504/ijnest.2020.10034469
S. Manna, Raj Kumar, K. N. Hareendran, S. Satpati, M. Sahu
The characteristics of UO2 powder are crucial for production of both UO2 based fuel and uranium based metallic and alloy fuel. Depending upon the usage as UO2 based fuel or as metallic uranium based fuel, the desired quality parameters of UO2 are different. The UO2 powder was produced by two different methods: (1) by the reduction of the thermal decomposed product of ammonium diuranate and (2) by the direct reduction of ammonium diuranate. Oxygen to uranium ratio (O/U), specific surface area (SSA) and crystal structure of UO2 powder produced by these two methods were studied.
{"title":"Comparative study on the properties of UO2 produced by direct reduction of ADU and reduction of calcined product of ADU","authors":"S. Manna, Raj Kumar, K. N. Hareendran, S. Satpati, M. Sahu","doi":"10.1504/ijnest.2020.10034469","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10034469","url":null,"abstract":"The characteristics of UO2 powder are crucial for production of both UO2 based fuel and uranium based metallic and alloy fuel. Depending upon the usage as UO2 based fuel or as metallic uranium based fuel, the desired quality parameters of UO2 are different. The UO2 powder was produced by two different methods: (1) by the reduction of the thermal decomposed product of ammonium diuranate and (2) by the direct reduction of ammonium diuranate. Oxygen to uranium ratio (O/U), specific surface area (SSA) and crystal structure of UO2 powder produced by these two methods were studied.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"181"},"PeriodicalIF":0.0,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47713832","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}
Pub Date : 2020-12-21DOI: 10.1504/ijnest.2020.10034467
Abdessamad DIDI, H. Amsil, K. Embarch, H. Bounouira, K. Laraki, H. Marah, H. Dekhissi
Safety measures play an important role in ensuring any system, although nuclear systems always require more safeguards than necessary. From this principle comes the importance of this research, which aims to conduct a study of neutron simulations and modelling to ensure safe installation of PGAA devices in the NB1 channel from the TRIGA Research Reactor at the Maamoura Center for Nuclear Studies. During this study, we used the Monte Carlo method using the MCNP6/X code. This study aims to determine the neutron profile, neutron distribution, and secondary gamma rays produced during the passage of the neutron flux in the collimator channel, sapphire and the vacuum channel that is maintained for the immediate neutron activation analysis (PGAA).
{"title":"Collimator and sapphire filter using for the prompt gamma neutron activation analysis facility: modelling and simulation","authors":"Abdessamad DIDI, H. Amsil, K. Embarch, H. Bounouira, K. Laraki, H. Marah, H. Dekhissi","doi":"10.1504/ijnest.2020.10034467","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10034467","url":null,"abstract":"Safety measures play an important role in ensuring any system, although nuclear systems always require more safeguards than necessary. From this principle comes the importance of this research, which aims to conduct a study of neutron simulations and modelling to ensure safe installation of PGAA devices in the NB1 channel from the TRIGA Research Reactor at the Maamoura Center for Nuclear Studies. During this study, we used the Monte Carlo method using the MCNP6/X code. This study aims to determine the neutron profile, neutron distribution, and secondary gamma rays produced during the passage of the neutron flux in the collimator channel, sapphire and the vacuum channel that is maintained for the immediate neutron activation analysis (PGAA).","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"154"},"PeriodicalIF":0.0,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47028786","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}
Pub Date : 2020-12-21DOI: 10.1504/ijnest.2020.10034460
Caio J.C.M.R. Cunha, F. A. Lima, D. Rodríguez
In the present work, we propose a three-dimensional model of the typical fuel assembly of the AP1000 reactor with the change from conventional fuel to (U, Th)O2. Owing to the complexity of the real model, we made some simplifications to reduce the computational cost and optimise the calculation time. The absence of spacer grids, burnable poisons, and the simulation of only 1/8 of the fuel assembly, culminated in a simplified model, and at the same time, capable of representing the reactor's operating situation under normal conditions. We obtained the power density distribution in the fuel assembly through a neutronic-thermohydraulic coupling, using MCNP6 and ANSYS CFX-19, respectively. One of the main differentials of this model is the consideration of the temperature dependence of thermophysical properties, which shows a direct influence on the results. We assessed the correlations published in some reports about thermal conductivity, density, and specific heat to obtain expressions for these parameters. We determined the temperature profiles, the axial distribution of the coolant density, and the pressure drop in the fuel assembly to assess the thermohydraulic limits. The proposed model presented results according to the project limits for the normal operating conditions of the reactor. The implementation of a robust model provided consistent results, in addition to a methodology capable of carrying out more complex analyses.
{"title":"Thermohydraulic evaluation of a MOX (U, Th)O2 fuel application in an AP1000 reactor typical fuel assembly","authors":"Caio J.C.M.R. Cunha, F. A. Lima, D. Rodríguez","doi":"10.1504/ijnest.2020.10034460","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10034460","url":null,"abstract":"In the present work, we propose a three-dimensional model of the typical fuel assembly of the AP1000 reactor with the change from conventional fuel to (U, Th)O2. Owing to the complexity of the real model, we made some simplifications to reduce the computational cost and optimise the calculation time. The absence of spacer grids, burnable poisons, and the simulation of only 1/8 of the fuel assembly, culminated in a simplified model, and at the same time, capable of representing the reactor's operating situation under normal conditions. We obtained the power density distribution in the fuel assembly through a neutronic-thermohydraulic coupling, using MCNP6 and ANSYS CFX-19, respectively. One of the main differentials of this model is the consideration of the temperature dependence of thermophysical properties, which shows a direct influence on the results. We assessed the correlations published in some reports about thermal conductivity, density, and specific heat to obtain expressions for these parameters. We determined the temperature profiles, the axial distribution of the coolant density, and the pressure drop in the fuel assembly to assess the thermohydraulic limits. The proposed model presented results according to the project limits for the normal operating conditions of the reactor. The implementation of a robust model provided consistent results, in addition to a methodology capable of carrying out more complex analyses.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"97"},"PeriodicalIF":0.0,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46345027","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}
Pub Date : 2020-12-21DOI: 10.1504/ijnest.2020.10034465
A. Hashim, F. A. Majeed
The radioactivity of alpha particles is a natural part of our daily life in which exposure to radiation activity is received by all people and which takes place naturally in food, water, and air. Ten different samples of edible oils of Turkish origin obtainable in the Iraqi market were examined using CR-39 nuclear solid-state tracks detectors to detect the radon exhalation rate and the effective radium content and uranium concentrations. The uranium concentration was found to vary from 0.051 ppm to 0.215 ppm and with an average value of 0.132 ppm. For samples, the content of effective radium varies from 345.366 mBq/kg to 1455.027 mBq/kg and with an average value of 900.196 mBq/kg. The mass exhalation rates of radon values differ from 2.610 mBq/kg.h to 10.998 mBq/kg.h, and with an average value 6 of .804 mBq/kg.h, while the rates of exhalation surface of radon differ from (3.076 to 12.958) mBq/m².h, with a mean value of 8.017 mBq/m².h. The results of this study do not represent a danger to people from the point of view of the health risks associated with radiation, being within the limits allowed internationally, as well as compared with the results of other studies, including various foods, by many researchers.
{"title":"Alpha radioactivity emitted from Turkish edible oils used in Iraqi kitchen","authors":"A. Hashim, F. A. Majeed","doi":"10.1504/ijnest.2020.10034465","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10034465","url":null,"abstract":"The radioactivity of alpha particles is a natural part of our daily life in which exposure to radiation activity is received by all people and which takes place naturally in food, water, and air. Ten different samples of edible oils of Turkish origin obtainable in the Iraqi market were examined using CR-39 nuclear solid-state tracks detectors to detect the radon exhalation rate and the effective radium content and uranium concentrations. The uranium concentration was found to vary from 0.051 ppm to 0.215 ppm and with an average value of 0.132 ppm. For samples, the content of effective radium varies from 345.366 mBq/kg to 1455.027 mBq/kg and with an average value of 900.196 mBq/kg. The mass exhalation rates of radon values differ from 2.610 mBq/kg.h to 10.998 mBq/kg.h, and with an average value 6 of .804 mBq/kg.h, while the rates of exhalation surface of radon differ from (3.076 to 12.958) mBq/m².h, with a mean value of 8.017 mBq/m².h. The results of this study do not represent a danger to people from the point of view of the health risks associated with radiation, being within the limits allowed internationally, as well as compared with the results of other studies, including various foods, by many researchers.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"133"},"PeriodicalIF":0.0,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48860867","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}
Pub Date : 2020-12-21DOI: 10.1504/ijnest.2020.10034462
A. Rabiee, A. Atf, A. Kamalinia
One of the most important issues in design of the nuclear fusion power plants is the heat removal from the hottest region at the divertor. Various methods could be employed in order to improve the heat transfer efficiency such as generating turbulent flow and injection of nanoparticles in the host fluid. In the current study, water/Al2O3 nanofluid forced swirl flow boiling has been investigated by using homogeneous thermophysical model within Eulerian-Eulerian framework through a twisted tape tube and boiling phenomenon was modelled using the Rensselear Polytechnic Institute approach. In addition to comparing the results with the experimental data and their reasonable agreement, it was evidenced that higher flow mixing results in more uniform bulk temperature and lower wall temperature along the twisted tape tube. The presence of Al2O3 nanoparticles in the boiling flow field showed that increasing the nanoparticle concentration leads to a reduced vapour volume fraction and wall temperature.
{"title":"Numerical investigation of Al2O3 nanoparticle effect on a boiling forced swirl flow field: application to the ITER project","authors":"A. Rabiee, A. Atf, A. Kamalinia","doi":"10.1504/ijnest.2020.10034462","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10034462","url":null,"abstract":"One of the most important issues in design of the nuclear fusion power plants is the heat removal from the hottest region at the divertor. Various methods could be employed in order to improve the heat transfer efficiency such as generating turbulent flow and injection of nanoparticles in the host fluid. In the current study, water/Al2O3 nanofluid forced swirl flow boiling has been investigated by using homogeneous thermophysical model within Eulerian-Eulerian framework through a twisted tape tube and boiling phenomenon was modelled using the Rensselear Polytechnic Institute approach. In addition to comparing the results with the experimental data and their reasonable agreement, it was evidenced that higher flow mixing results in more uniform bulk temperature and lower wall temperature along the twisted tape tube. The presence of Al2O3 nanoparticles in the boiling flow field showed that increasing the nanoparticle concentration leads to a reduced vapour volume fraction and wall temperature.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"114"},"PeriodicalIF":0.0,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47896001","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}
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