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1.
This report presents the results and recommendations of the U. S. Department of Energy Fusion Energy Advisory Committee (FEAC) review of its Inertial Fusion Energy (IFE) program. The subpanel charged with the review was chaired by John Sheffield of Oak Ridge National Laboratory. The FEAC, to which the subpanel reported, was chaired by Robert Conn of the University of California at San Diego.  相似文献   

2.
There are several topics that require resolution prior to the construction of an Inertial Fusion Energy [IFE] laboratory Engineering Test Facility [ETF]: a pellet that produces high gain; a pellet fabrication system that cost-effectively and rapidly manufactures these pellets; a sufficiently uniform and durable high repetition-rate laser pellet driver; a practical target injection system that provides accurate pellet aiming; and, a target chamber that will survive the debris and radiation of repeated high-gain pellet implosions. In this summary we describe the science issues and opportunities that are involved in the design of a successful high gain direct drive Inertial Confinement Fusion [ICF] pellet.  相似文献   

3.
This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) in response to a charge letter from Dr. Ray Orbach (Appendix A). In that letter, Dr. Orbach asked FESAC for an assessment of the present status of inertial fusion energy (IFE) research carried out in contributing programs. These programs include the heavy ion (HI) beam, the high average power laser (HAPL), and Z-Pinch drivers and associated technologies, including fast ignition (FI). This report, presented to FESAC on March 29, 2004, and subsequently approved by them (Appendix B), presents FESAC's response to that charge.  相似文献   

4.
Presentations from a Fusion Power Associates symposium, The Fusion Energy Option, are summarized. The topics include perspectives on fossil fuel reserves, fusion as a source for hydrogen production, status and plans for the development of inertial fusion, planning for the construction of the International Thermonuclear Experimental Reactor, status and promise of alternate approaches to fusion and the need for R&D now on fusion technologies.  相似文献   

5.
可加工SiO2气凝胶及其惯性约束聚变靶微柱制备   总被引:1,自引:0,他引:1  
以正硅酸乙酯(TEOS)为前驱体,采用酸碱两步催化法制备SiO2醇凝胶。醇凝胶分别经TEOS母液、六甲基二硅胺烷(HMDSA)处理后,采用CO2超临界干燥法制备出密度在30~100mg/cm3的SiO2气凝胶。用傅立叶变换红外光谱(FTIR)对疏水性SiO2气凝胶进行了表征,并用扫描电镜图研究了气凝胶改性前后的微观网络结构。改性后的气凝胶微观骨架变大,部分细小的网络结构消失。改性后的气凝胶在潮湿环境中具有极好的尺寸稳定性和疏水性能。用精密车床加工出了满足惯性约束聚变物理试验要求的ICF靶微柱。  相似文献   

6.
惯性约束聚变低温冷冻氘氚靶制备技术   总被引:1,自引:0,他引:1  
低温冷冻氘氚靶对于惯性约束聚变研究至关重要,主要有塑料微球靶、金属铍球靶、泡沫球壳靶等。根据微球球壳材质的不同,采用不同的低温冷冻氘氚靶制备技术。塑料微球靶采用“高压充氘氚-冷冻法”或“充气管充气法”;金属铍球靶采用“低温、低压冷凝法”或“高温、高压扩散连接半球壳法”;多孔泡沫球壳靶采用“球壳材料吸附氘氚液体法”。本文简述上述技术和方法的发展状况和趋势。  相似文献   

7.
基于超高强流加速器轰击氘氚球靶可实现可控核聚变,但相关的装置非常庞大,以至于到目前仍不能建造。近年来,随着强流加速器技术的快速发展,尤其是激光离子源和单腔多束型加速器的发展,使得实现重离子惯性约束核聚变成为可能。本文介绍了重离子惯性约束核聚变注入器的新设计,尤其是低能段和中能段单腔多束型加速器的设计,为重离子惯性约束核聚变提供技术支持。  相似文献   

8.
ICF靶中的纳米金属功能材料研究进展   总被引:1,自引:1,他引:1  
本文介绍了中国工程物理研究院激光聚变研究中心在激光惯性约束聚变(ICF)和强辐射源材料研究中涉及到的一些纳米金属功能材料的最新研究进展。主要包括自悬浮定向流金属纳米粉末材料制备与性能研究,介质阻挡放电金属纳米粉末表面包覆研究,真空热压成型的纳米晶体材料研究,以及低密度高孔隙率的泡沫镍金属材料、纳米多孔Cu材料和Au泡沫材料研究;在团簇材料、纳米成型材料研究方面,涉及到了过渡金属、贵金属小团簇材料的几何构型和静电极化率特性的理论模拟研究,以及三角形、六边形、棒状、立方体等特殊纳米结构和形状的Ag、Au金属纳米激光X光转换材料研究。  相似文献   

9.
The rationale for an expanded effort on the development of inertial fusion as an energy source is discussed. It is argued that there should be a two-pronged, complementary approach to fusion energy development over the next two to three decades: (1) Magnetic Fusion (MFE) via ITER and the supporting magnetic domestic program and (2) Inertial Fusion (IFE), a credible, affordable approach that exploits unique US strengths and current world leadership. IFE is only a few years away from demonstration of single-shot ignition and fusion energy gain via NIF. Enhanced funding for IFE R&D is needed in the near-term in order to prepare to expeditiously proceed beyond NIF to the energy application of inertial fusion.  相似文献   

10.
This paper summarizes recent progress in fusion Innovative Confinement Concepts (ICC) as reported at the 2004 ICC Workshop held May 25–28, 2004 in Madison, Wisconsin. This was the third in an annual series of workshops on this topic. The purpose of these workshops is to provide a forum for those who are thinking and working beyond what is considered to be the current state of understanding of fusion concepts.  相似文献   

11.
This paper summarizes safety and environmental issues of Inertial Fusion Energy (IFE): inventories, effluents, maintenance, accident safety, waste management, and recycling. The fusion confinement approach among inertial and magnetic options affects how the fusion reaction is maintained and which materials surround the reaction chamber. The target fill technology has a major impact on the target factory tritium inventory. IFE fusion reaction chambers usually employ some means to protect the first structural wall from fusion pulses. This protective fluid or granular bed also moderates and absorbs most neutrons before they reach the first structural wall. Although the protective fluid activates, most candidate fluids have low activation hazard. Hands-on maintenance seems practical for the driver, target factory, and secondary coolant systems; remote maintenance is likely required for the reaction chamber, primary coolant, and vacuum exhaust cleanup systems. The driver and fuel target facility are well separated from the main reaction chamber.  相似文献   

12.
Heavy-ion-driven fusion (HIF) is a scheme to achieve inertial confinement fusion (ICF). Investigation of the non-uniformity of heavy-ion beam (HIB) irradiation is one of the key issues for ICF driven by powerful heavy-ion beams. Ions in HIB impinge on the pellet surface and deposit their energy in a relatively deep and wide area. Therefore, the non-uniformity of HIB irradiation should be evaluated in the volume of the deposition area in the absorber layer. By using the OK1 code with some corrections, the non-uniformityof heavy-ion beam irradiation for the different ion beams on two kinds of targets were evaluated in 12-, 20-, 60- and 120-beam irradiation schemes. The root-mean-square (RMS) non-uniformity value becomes σRMS= 8. 39% in an aluminum mono-layer pellet structure and σRMS= 6.53% in a lead-aluminum layer target for the 12-uranium-beam system. The RMS non-uniformity for the lead-aluminum layer target was lower than that for the mono-layer target. The RMS and peak-to-valley (PTV) non-uniformities are reduced with the increase in beam number, and low at the Bragg peak layer.  相似文献   

13.
Presentations from a Fusion Power Associates symposium, Fusion and Energy Policy, are summarized. The topics include an overview of U.S. Department of Energy policies, fusion strategies in Europe and Japan, plans for U.S. participation in the construction of ITER, status of construction of the National Ignition Facility and recent progress in all aspects of magnetic and inertial fusion.  相似文献   

14.
Although the safety and environmental (S & E) characteristics of fusion energy have long been emphasized, these benefits are not automatically achieved. To maximize the potential S & E attractiveness of the inertial fusion energy (IFE), analyses must be performed early in the designs so that lessons can be learned and intelligent decisions made. In this work we have introduced for the first time heat transfer and thermal-hydraulics calculations as part of a state-of-the-art set of codes and libraries in order to establish an updated methodology for IFE safety analysis. We have focused our efforts primarily on two IFE power plant conceptual designs: HYLIFE-II and SOMBRERO. To some degree, these designs represent the extremes in IFE power plant designs. Also, a preliminary safety assessment has been performed for a generic target fabrication facility producing various types of targets and using various production techniques. Although this study cannot address all issues and hazards posed by an IFE power plant, it advances our understanding of radiological safety of such facilities. This will enable better comparisons between IFE designs and competing technologies from the safety point of view.  相似文献   

15.
This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) in response to a charge letter dated September 10, 2002 from Dr. Ray Orbach, Director of the DOE's Office of Science. In that letter, Dr. Orbach asked FESAC to develop a plan with the end goal of the start of operation of a demonstration power plant in approximately 35 years. This report, submitted March 5, 2003, presents such a plan, leading to commercial application of fusion energy by mid-century. The plan is derived from the necessary features of a demonstration fusion power plant and from the time scale defined by President Bush. It identifies critical milestones, key decision points, needed major facilities and required budgets. The report also responds to a request from DOE to FESAC to describe what new or upgraded fusion facilities will best serve our purposes over a time frame of the next twenty years.  相似文献   

16.
激光惯性约束聚变裂变混合能源包层中子学数值模拟   总被引:1,自引:1,他引:0  
对三维输运与燃耗耦合程序MCORGS进行了适应性改造,并对利弗莫尔实验室提出的激光惯性约束聚变裂变混合能源(LIFE)概念进行了分析和改进。输运计算采用MCNP程序,燃耗计算采用ORIGENS程序,增加氚控制模块和功率控制模块。建立了与LIFE等价的以贫化铀为燃料、Be为中子增殖剂的包层方案,通过数值模拟验证了MCORGS程序的可靠性。针对Be资源短缺及冷却复杂问题,设计了以贫化铀为燃料、Pb为中子增殖剂的包层方案,包层能量放大了4倍,可在55a内稳定输出2 000 MWt功率。  相似文献   

17.
In December 1998, Secretary of Energy Bill Richardson asked the Secretary of Energy Advisory Board to form a Task Force on Fusion Energy to conduct a review of the Department's fusion energy technologies, both inertial and magnetic, and to provide recommendations as to the role of these technologies as part of a national fusion energy research program. This report reflects the Task Force's response to the request.  相似文献   

18.
本工作基于靶丸全球面测量的经纬迹线法,应用由原子力显微镜、精密回转气浮轴系及辅助转位轴系等组成的靶丸表面形貌测量系统,对直径0.34mm的空心塑料靶丸表面进行了测量实验。实验选择了圆周9条经圆(间隔20°),每个经圆方向上纬圆间隔10μm,最大偏移20μm的方案,获取了靶丸全球面的经纬测量迹线,并对测量结果进行了模数-功率谱特征曲线和表面均方根粗糙度的分析。  相似文献   

19.
In October 2003, Dr. Raymond Orbach, Director of the Department of Energy’s Office of Science, issued a charge to the Fusion Energy Sciences Advisory Committee (FESAC) “to identify the major science and technology issues that need to be addressed, recommend how to organize campaigns to address these issues, and recommend the priority order for these campaigns.” The sections in this report document the results of the Panel’s work. The first two sections describe the concepts of the overarching themes, topical scientific questions, and campaigns. The next six sections (Sections 3–8) describe in detail the six scientific campaigns. Section 9 describes some important enabling research activities necessary for the campaigns. Sections 10–12 describe the overarching themes, which provide a crosscutting perspective of the activities in the six campaigns. Finally, the Panel’s recommendations are set forth in Section 13. The charge letter to the panel is provided as Appendix A; the FESAC response letter is provided as Appendix D.  相似文献   

20.
This report of the Integrated Program Planning Activity (IPPA) has been prepared in response to a recommendation by the Secretary of Energy Advisory Board that, Given the complex nature of the fusion effort, an integrated program planning process is an absolute necessity. We therefore undertook this activity to integrate the various elements of the program, to improve communication and performance accountability across the program, and to show the interconnectedness and interdependency of the diverse parts of the national Fusion Energy Sciences Program. This report is based on the September 1999 Fusion Energy Sciences Advisory Committee's (FESAC) report Priorities and Balance within the Fusion Energy Sciences Program. In its December 5, 2000, letter to the Director of the Office of Science, the FESAC reaffirmed the validity of the September 1999 report and stated that the IPPA presents a framework and process to guide the achievement of the 5-year goals listed in the 1999 report. The report also outlines a process for establishing a database for the fusion research program that will indicate how each research element fits into the overall program. This database will also include near-term milestones associated with each research element and will facilitate assessments of the balance within the program at different levels.  相似文献   

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