Pub Date : 2019-01-26DOI: 10.5772/INTECHOPEN.80582
F. A. Majeed, Yousif A. Abdul-Hussien, Fatima M. Hussian
Semiclassical and full quantum mechanical approaches are used to study the effect of channel coupling on the calculations of the total fusion reaction cross section σ fus and the fusion barrier distribution D fus for the systems 6 Li + 64 Ni, 11 B + 159 Tb, and 12 C + 9 Be. The semiclassical approach used in the present work is based on the method of the Alder and Winther for Coulomb excitation. Full quantum coupled-channel calculations are carried out using CCFULL code with all order coupling in comparison with our semiclassical approach. The semiclassical calculations agree remarkably with the full quantum mechanical calculations. The results obtained from our semiclassical calculations are compared with the available experimental data and with full quantum coupled-channel calculations. The comparison with the experimental data shows that the full quantum coupled channels are better than semiclassical approach in the calculations of the total fusion cross section σ fus and the fusion barrier distribution D fus .
采用半经典和全量子力学方法研究了通道耦合对6 Li + 64 Ni、11 B + 159 Tb和12 C + 9 Be体系总聚变反应截面σ fus和聚变势垒分布D fus计算的影响。本文所采用的半经典方法是基于阿尔德和温特的库仑激励方法。与我们的半经典方法相比，使用全阶耦合的CCFULL码进行了全量子耦合信道计算。半经典计算与全量子力学计算非常一致。我们的半经典计算结果与现有的实验数据和全量子耦合信道计算结果进行了比较。与实验数据的比较表明，全量子耦合通道在计算总熔合截面σ fus和熔合势垒分布D fus方面优于半经典方法。
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Pub Date : 2019-01-09DOI: 10.5772/INTECHOPEN.82335
Q. Haider
The declining reserves of fossil fuels and their detrimental effects on the environment have thrust nuclear power based on fission reaction into the limelight as a promising option to energy-starved economies around the world. However, the 1986 Chernobyl and 2011 Fukushima accidents have heightened our fears about nuclear technology ’ s ability to provide a safe way of generating clean power. There is another kind of nuclear energy that has been powering the Sun and stars since their formation. It is nuclear fusion — a process in which two lighter nuclei, typically isotopes of hydrogen, combine together under conditions of extreme pressure and temperature to form a heavier nucleus. In this chapter, harnessing the energy produced in nuclear fusion reaction in a laboratory environment is discussed. Various research programs dedicated to building fusion reactors are also discussed. Emphasis is given on over-coming some of the technological challenges, such as surmounting the Coulomb barrier, confining the plasma, and achieving the “ ignition ” temperature for fusion.
{"title":"Nuclear Fusion: Holy Grail of Energy","authors":"Q. Haider","doi":"10.5772/INTECHOPEN.82335","DOIUrl":"https://doi.org/10.5772/INTECHOPEN.82335","url":null,"abstract":"The declining reserves of fossil fuels and their detrimental effects on the environment have thrust nuclear power based on fission reaction into the limelight as a promising option to energy-starved economies around the world. However, the 1986 Chernobyl and 2011 Fukushima accidents have heightened our fears about nuclear technology ’ s ability to provide a safe way of generating clean power. There is another kind of nuclear energy that has been powering the Sun and stars since their formation. It is nuclear fusion — a process in which two lighter nuclei, typically isotopes of hydrogen, combine together under conditions of extreme pressure and temperature to form a heavier nucleus. In this chapter, harnessing the energy produced in nuclear fusion reaction in a laboratory environment is discussed. Various research programs dedicated to building fusion reactors are also discussed. Emphasis is given on over-coming some of the technological challenges, such as surmounting the Coulomb barrier, confining the plasma, and achieving the “ ignition ” temperature for fusion.","PeriodicalId":149018,"journal":{"name":"Nuclear Fusion - One Noble Goal and a Variety of Scientific and Technological Challenges","volume":"80 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127188298","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 : 2018-12-31DOI: 10.5772/INTECHOPEN.82349
Donghua Yue, Xingyi Zhang, Youhe Zhou
Cable-in-conduit conductor (CICC) has wide applications, and this structure is often served to undergo heat force-electromagnetic coupled field in practical utiliza-tion, especially in the magnetic confinement fusion (e.g., Tokamak). The mechanical behavior in CICC is of relevance to understanding the mechanical response and cannot be ignored for assessing the safety of these superconducting structures. In this chapter, several mechanical models were established to analyze the mechanical behavior of the CICC in Tokamak device, and the key mechanical problems such as the equivalent mechanical parameters of the superconducting cable, the untwisting behavior in the process of insertion, the buckling behavior of the superconducting wire under the action of the thermo-electromagnetic static load, and the Tcs (current sharing temperature) degradation under the thermo-electromagnetic cyclic loads are studied. Finally, we summarize the existing problems and the future research points on the basis of the previous research results, which will help the related researchers to figure out the mechanical behavior of CICC more easily.
{"title":"The Mechanical Behavior of the Cable-in-Conduit Conductor in the ITER Project","authors":"Donghua Yue, Xingyi Zhang, Youhe Zhou","doi":"10.5772/INTECHOPEN.82349","DOIUrl":"https://doi.org/10.5772/INTECHOPEN.82349","url":null,"abstract":"Cable-in-conduit conductor (CICC) has wide applications, and this structure is often served to undergo heat force-electromagnetic coupled field in practical utiliza-tion, especially in the magnetic confinement fusion (e.g., Tokamak). The mechanical behavior in CICC is of relevance to understanding the mechanical response and cannot be ignored for assessing the safety of these superconducting structures. In this chapter, several mechanical models were established to analyze the mechanical behavior of the CICC in Tokamak device, and the key mechanical problems such as the equivalent mechanical parameters of the superconducting cable, the untwisting behavior in the process of insertion, the buckling behavior of the superconducting wire under the action of the thermo-electromagnetic static load, and the Tcs (current sharing temperature) degradation under the thermo-electromagnetic cyclic loads are studied. Finally, we summarize the existing problems and the future research points on the basis of the previous research results, which will help the related researchers to figure out the mechanical behavior of CICC more easily.","PeriodicalId":149018,"journal":{"name":"Nuclear Fusion - One Noble Goal and a Variety of Scientific and Technological Challenges","volume":"49 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132340883","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 : 2018-11-05DOI: 10.5772/INTECHOPEN.81582
Rong Liu
Thorium is a fertile element that can be applied in the conceptual blanket design of a fusion-fission hybrid energy reactor, in which 232 Th is mainly used to breed 233 U by capture reaction. It is essential to validate 232 Th nuclear data by carrying out integral fusion neutronics experiments for macroscopic thorium assemblies. The thorium assemblies with a D-T fusion neutron source consist of a polyethylene shell, depleted uranium shell, and thorium oxide cylinder. The activation of γ -ray off-line method for determining the thorium reaction rates is developed. The 232 Th(n, γ ), 232 Th(n, f), and 232 Th(n, 2n) reaction rates in the assemblies are measured by using ThO 2 foils and an HPGe γ spectrometer. From 232 Th reaction rates, the fuel and neutron breeding properties of thorium under different neutron spectra are obtained and compared. The leakage neutron spectra from the ThO 2 cylinders are measured by a liquid scintillation detector. The experimental uncertainties are analyzed. The experiments are simulated by using the MC code with different evaluated data. The ratios of calculation to experimental values are analyzed.
{"title":"Fusion Neutronics Experiments for Thorium Assemblies","authors":"Rong Liu","doi":"10.5772/INTECHOPEN.81582","DOIUrl":"https://doi.org/10.5772/INTECHOPEN.81582","url":null,"abstract":"Thorium is a fertile element that can be applied in the conceptual blanket design of a fusion-fission hybrid energy reactor, in which 232 Th is mainly used to breed 233 U by capture reaction. It is essential to validate 232 Th nuclear data by carrying out integral fusion neutronics experiments for macroscopic thorium assemblies. The thorium assemblies with a D-T fusion neutron source consist of a polyethylene shell, depleted uranium shell, and thorium oxide cylinder. The activation of γ -ray off-line method for determining the thorium reaction rates is developed. The 232 Th(n, γ ), 232 Th(n, f), and 232 Th(n, 2n) reaction rates in the assemblies are measured by using ThO 2 foils and an HPGe γ spectrometer. From 232 Th reaction rates, the fuel and neutron breeding properties of thorium under different neutron spectra are obtained and compared. The leakage neutron spectra from the ThO 2 cylinders are measured by a liquid scintillation detector. The experimental uncertainties are analyzed. The experiments are simulated by using the MC code with different evaluated data. The ratios of calculation to experimental values are analyzed.","PeriodicalId":149018,"journal":{"name":"Nuclear Fusion - One Noble Goal and a Variety of Scientific and Technological Challenges","volume":"42 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129007483","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 : 2018-11-05DOI: 10.5772/INTECHOPEN.81518
I. Aleksandrova, E. Koresheva, E. Koshelev, B. Kuteev, A. Nikitenko
Target production and its delivery into the reaction chamber of high repetition rate facilities are the most challenging issues in inertial fusion energy (IFE) research. At the Lebedev Physical Institute of Russian Academy of Sciences (LPI), efforts are underway on creation of the mechanical mockup of IFE reactor (MM-IFE) for developing the reactor-scale technologies applicable to mass production of IFE targets and their delivery with a repeatable rate into the chamber of IFE reactor. In this chapter, we discuss the current status and further trends of developments in the area of advanced target technologies underlying the research and development program on MM-IFE.
{"title":"Mechanical Mockup of IFE Reactor Intended for the Development of Cryogenic Target Mass Production and Target Rep-Rate Delivery into the Reaction Chamber","authors":"I. Aleksandrova, E. Koresheva, E. Koshelev, B. Kuteev, A. Nikitenko","doi":"10.5772/INTECHOPEN.81518","DOIUrl":"https://doi.org/10.5772/INTECHOPEN.81518","url":null,"abstract":"Target production and its delivery into the reaction chamber of high repetition rate facilities are the most challenging issues in inertial fusion energy (IFE) research. At the Lebedev Physical Institute of Russian Academy of Sciences (LPI), efforts are underway on creation of the mechanical mockup of IFE reactor (MM-IFE) for developing the reactor-scale technologies applicable to mass production of IFE targets and their delivery with a repeatable rate into the chamber of IFE reactor. In this chapter, we discuss the current status and further trends of developments in the area of advanced target technologies underlying the research and development program on MM-IFE.","PeriodicalId":149018,"journal":{"name":"Nuclear Fusion - One Noble Goal and a Variety of Scientific and Technological Challenges","volume":"76 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-11-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124416739","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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