氘团簇离子（d^＋3）与固体相互作用过程中的团簇行为研究

讨论了由三个氘原子组成的氘团簇离子束与独立氘离子束在轰击固体靶时,在原子过程呼Ｄ－Ｄ核聚变过程中体现出的差别。对氘团簇与固体靶相互作用的机理进行了分析。     

^197Au束轰击TiD靶引起的D—D熔合研究

测量了能量范围从１．０ＭｅＶ到５．２ＭｅＶ的＾１９７Ａｕ束轰击ＴｉＤ靶引发的Ｄ（ｄ，ｐ）Ｔ反应的质子产额曲线，为了对其进行解释，根据两步级联磁撞模型的框架编写的ＴＳＣＣＦＣ程序进行了相应的计算，发现计算结果与结果在误差范围内能较好地符合。     

Reaction balance and efficiency analysis of a D-D fusion/fission hybrid with satellite D-3He reactors

Selected reactor physics and isotope balance characteristics of a fusion hybrid supported D-³He satellite nuclear energy system are formulated and investigated. The system consists of two types of reactors: a parent D-fueled fusion device and a number of smaller reactors optimized for D-³He fusion. The parent hybrid station breeds the helium-3 for the satellites and also breeds fissile fuel for an existing fission reactor economy. Various hybrid operational regimes are examined in order to determine favorable reactorQ values and effective fusion and fission efficiencies. A number of analytical correlations between power output, plasma energetics, blanket neutronics, breeding capacity, and energy conversion cycles are established and evaluated. Numerical examples of performance parameters such as fission-to-fusion power, overall conversion efficiency, and the ratio of satellite to parent fusion power are presented. The range of reactor efficiencies is elucidated as affected by the internal plasma power balances. As an upper bound based on optimistic injection and direct conversion efficiencies, we find the D-³He satellite system power output attaining at best 1/3 of the parent fusion power.     

Simulation of Multigroup X-Ray,Alpha-Particle and Neutron Transport in Ion Beam Driven ICF Target

A one-dimensional Lagrangian code, MEDUSA-IB for the analysis of ion beam fusion target behavior was developed. The code included multigroup X-ray, α-particle and neutron transport models. Photon transport equation was solved by variable Eddington method. Particle tracking method and collision probability method were used for the simulation of α-particle and neutron transport respectively. Temperature dependent ion beam energy deposition was also considered. Each routine of the code was verified separately. The analysis of a bare 1 mg DT target after ignition showed that only neutron transport slightly decreases fusion yield. The analysis of a reactor-size hollow single shell target containing 4.2 mg DT fuel, UTLIF target showed: Radiation and α-particle transport, temperature dependence of ion beam stopping and the equation of states decreased fusion gain when they were considered accurately. Neutron transport slightly increased the gain. The momentum deposition of ion beam and α-particles had very slight effects.     

Report on the Fifth Symposium on Current Trends in International Fusion Research

The Fifth Symposium on Current Trends in International Fusion Research was held on 24–29 March 2003 in Washington, USA in co-operation with the International Atomic Energy Agency (IAEA). Well-known scientists in their field of interest in fusion research were invited to present review papers. The presentations covered a broad range of fusion topics, including inertial confinement fusion, electrostatic confinement, various magnetic confinement schemes, and hybrid schemes. Each session chairman composed a session report, which John Pucadyil used to create this Report on the Fifth Symposium.