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Fusion-Fission Hybrid Reactor in Energy Resource Strategy and Analysis for Hybrid Design
LIU Chengan, SHI Xueming
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    2010, 27 (3): 433-438.  
Abstract226)      PDF (309KB)(754)      
Fusion-fission hybrid reactor in a long term energy resource strategy is described briefly.Capability of electricity and fissionable material production of a hybrid reactor consisted of typical fusion reactor core and blanket is analyzed emphatically.Capability of electricity production of composite fuel cycle system of hybrid and satellite reactors (e.g.PWR) is studied.Related calculations show that a natural uranium fueled and water cooled blanket is economical and less technical risk.
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Physical Considerations in Deuterium Fusion Explosion Cave Design for Power Generation
LIU Chengan
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    2008, 25 (1): 15-21.  
Abstract254)      PDF (379KB)(669)      
Physical considerations in explosion cave design of 10 kt TNT nuclear explosion of deuterium fusion are analyzed. The lowest quantity of heat carrier(sodium) is estimated. Physical factors affecting sodium vaporization and damping shock waves are analyzed. The action intensity in the nonstationary process of nuclear explosion——shock waves on the outer wall and durability of outer wall are qualitatively evaluated.
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COMPUTATION AND ANALYSIS ON THE WARHEAD DETECTION
Wu Jun, Liu Chengan, Ren Jie
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1997, 14 (S1): 530-534.  
Abstract177)      PDF (142KB)(799)      
The γ ray transport process in some pits of warhead models has been studied.Since the penetrating γ ray spectra are different for different models,the feasibility of using the γ ray from fissile materials as the fingerprint of the warhead has been analyzed.By comparing the characteristics of γ ray's intensities,the thickness of bare ball of Wg.Pu can be estimated if its thickness is less than 1.5 cm.
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THE EFFECT OF MEDIUM MOTION ON NEUTRON TRANSPORT AND ITS CALCULATION STUDIES Part 2. The Problem for Neutron Transport Equation in Speed Flowin Medium and Its Computational Study
Liu Chengan, Huang Wenkai, Tian Dongfeng
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1996, 13 (3): 305-309.  
Abstract237)      PDF (182KB)(729)      
The problem of neutron Transport equation in speed flowing medium is outhined The equation of neutron transport in flowing medium is derived and the computer code is developed Taking a ideal high criticality system as an example, numerical results for the given velocity field are presented. The effect of speed flow of medium on the reactivity of system(time constant of neutron multiplication) is also analysed.
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A COMPARISON BETWEEN THE FAST-FISSION BLANKETAND THE SUPPRESSED-FISSION BLANKETOF FUSION-FISSION HYBRID REACTOR
Liu Chengan
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1993, 10 (1): 20-24.  
Abstract218)      PDF (315KB)(701)      
For the fusion-fission hybrid Reactor producing nuclear fuel as its main purpose, the two distinct design could be adopted: fast-fission blanket and suppressed-fission blanket. They possess both individual advantage and deficiencies.Taking the two typical blanket configuration as examples, the neutronics calculation and the contrast analysis have been performed.The results in this paper could be taken for reference when doing conceptual design and study of a technological feasibility, a safety and economics.
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