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Using Super-high Energy Neutrons to Detect Inertial Confinement Fusion
LI Shu, TIAN Dongfeng, DENG Li
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2012, 29 (
1
): 82-86.
Abstract
(
345
)
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(278KB)(
1109
)
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In inertial confinement fusion (ICF) target, collision between fusion neutrons may produce super-high energy neutrons. A relationship between velocity of fusion and ratio of generated super-high energy neutron is derived. An ideal fusion model is simulated by numerical method. It indicates that the ratio of generated super-high energy neutron is increased sharply as burning volume of DT is decreased. With this information, 2D-effect and mixing-effect during compression of target are deduced with escaped super-high energy neutrons. Furthermore, a relationship between velocity of burning T and ratio of generated super-high energy neutron is concluded. It shows that using super-high energy neutron to detect ICF is effective.
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High Efficiency Monte Carlo Sample Method for Super-high Energy Neutrons
LI Shu, TIAN Dongfeng, DENG Li
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2011, 28 (
3
): 323-328.
Abstract
(
309
)
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(309KB)(
1256
)
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An adding weight sample method is developed for neutron transportation in inertial confinement fusion.It aims to increase samples in important zone and decrease samples in non-important zone.Weight of each sample is corrected for keeping calculated results non-bias.Typical model is simulated.It indicates that the method improves effectively neutron samples in fusion zone,while collisions between neutrons increase obviously.Calculation error of super-high energy neutron flux is decreased remarkably.Calculation efficiency of super-high energy neutrons is improved.
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Super-high Energy Neutrons Produced by Neutron Collision
LI Shu, TIAN Dongfeng, DENG Li
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2010, 27 (
5
): 717-721.
Abstract
(
379
)
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(230KB)(
1098
)
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Relationship between super-high energy neutrons and collisions is derived.Monte Carlo method is used to decide speed of neutrons after collision.A code applicable to nonlinear neutron transport problem is developed to simulate neutron collision and transportation.Numerical calculation indicates that production rate of super-high energy neutrons is in linear relationship with the square of neutron source intensity.
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Monte Carlo Method for Nonlinear Neutron Transport
LI Shu, TIAN Dongfeng, DENG Li
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2008, 25 (
4
): 477-482.
Abstract
(
277
)
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(292KB)(
1177
)
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An approximate linearization method is proposed for nonlinear neutron transport equations. The equation is deduced to a form suitable for Monte Carlo simulations. Numerical results show that it is reasonable. It provides a tool for simulating high energy neutron transportation.
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One Body Density Matrix of Nucleus in the Shell Model
HU Zehua, SUN Weili, TIAN Dongfeng, ZHANG Benai
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2007, 24 (
6
): 733-739.
Abstract
(
386
)
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(240KB)(
1237
)
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A method calculating one body density matrix of nucleus in the mean field shell model is proposed.One body density matrixes of double closed nuclei
40
Ca,
90
Zr are calculated. The nucleon density and momentum distributions are calculated and compared with those by the Hatree-Fock-Bogolubov theory,local Fermi gas model and those by experiments,respectively.
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NUMERICAL SIMULATION STUDY FOR 3D GAS FLOW IN ENGINE CYLINDER BY ALE METHOD
Liang Shuqing, Zhang Zhaoqun, Wei Defu, Tian Dongfeng
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 1997, 14 (
S1
): 553-555.
Abstract
(
294
)
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(145KB)(
1074
)
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It is an important research program based on numerical simulation for studying gas flow in engine cylinder to find a reasonal way of arranging gas flow efficiently. In this paper, a 3D Arbitrary Lagrange Euler (ALE) method is studied for this problem by developing KIVA Ⅱ. Some numerical simulation results are given for an example.
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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.
Abstract
(
273
)
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(182KB)(
1025
)
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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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