neutron-flux 中文意思是什麼
neutron-flux
解釋
中子通量-
According to the requirements of the cng on neutron flux, critical wavelength and distance between inpile guides and the cns, the relation between the source size and the critical angle of the coating material of the inpile guides as well as neutron flux at exit of the cngs have been studied
根據導管設計指標的需要，研究了冷源尺寸與堆內導管內壁鍍膜材料的全反射臨界角和導管系統出口處中子注量率的關系。 -
Logarithmic power measuring assembly based on the neutron flux density
根據中子通量密度的對數功率測量裝置 -
The performance of the cngs, including transmission efficiency, neutron flux, flux spectrum, divergency, uniform and gravity effect, have been analysed technically. that the scheme of supermirror guide is optimum has been given and adopted
在此基礎上，分別從傳輸效率、中子注量率、譜形、發散度、均勻性和重力影響方面，對導管性能進行了技術分析，提出了超鏡導管是建設的最佳方案，並被工程設計采納。 -
The position and size of the monochromator, focusing curvature radii and tilting angles of the germanium focusing monochromator under different different take - off angle, size and divergency of the second collimator and intensity loss due to the use of it were determined. the neutron flux at different wavelength, under different reflection and take - off angle of the monochromator and divergency of the first collimator, were given. the simulation on the aperture used for limiting beam size in front of the sample showed that, smaller the size of the aperture and further the distance from the aperture to the sample, greater the loss of the intensity and more serious the spread of the beam along vertical direction at the sample position which makes the practical sampling volume greater than expected
用蒙特卡羅模擬方法對中子應力衍射譜儀的設計方案進行了優化研究，提出了一系列可供參考的數據：確定了單色器的位置、尺寸、垂直聚焦單色器在不同起飛角下的聚焦曲率半徑和傾角；討論了第二準直器的尺寸和發散，以及使用第二準直器造成的強度損失；給出了在不同單色器反射面、起飛角、中子波長和第一準直器發散度的情況下樣品處的中子注量率，以及多種組合情況下譜儀的解析度曲線；對限束方孔的尺寸、距離樣品遠近對強度損失和測量中的影響做了深入研究。 -
According to the demand of the concept design of china spallation neutron source ( csns ), the target station, i. e. the target, the reflector and the moderator have been simulated and optimized using monte carlo simulation software, nmtc / jam and mcnp4a, firstly. the neutron flux escaping from the target and the moderator and the heat deposition in the target, the reflector and the moderator are calculated. these results provided essential data as a basis of the spallation neutron source design
本論文結合當前中國散裂中子源（ chinaspallationneutronsource ， csns ）工程概念設計的迫切需要，選擇國際上廣泛使用的基於蒙特?卡羅方法，用於模擬粒子輸運過程的程序mcnp4a和nmtc jam作為研究工具，首次對csns靶站進行了全面的模擬與優化，內容包括靶、反射體與慢化器系統的中子通量分佈以及熱量沉積，同時計算了靶的溫度場與應力場分佈。 -
The reflector can increase the neutron flux obviously and the main processes of the neutron yield in reflector are spallation reaction induced by energetic hadrons and ( n, 2n ) reaction. when the moderator height is equal to the distance between the upper part and the lower part of the split target, the total neutron flux of the split target will be higher by 20. 1 % than that of the integral one. secondly, the high - energy neutron escaping from the target will enter into the moderator and be slowed down
得到經水慢化器慢化后，中子通量在慢化器厚度與高度方向上的分佈；比較了水與液態氫的慢化能力以及中子在水、液態氫、液態甲烷這三種慢化器慢化后的能譜；在csns的靶站設計中，引出慢中子的導管不完全位於慢化器中子引出面的法線方向上，因此進一步計算了中子通量角分佈。 -
Measurement of neutron flux in cfbr - reactor
堆中子注量測量 -
Project on neutron flux density data acquisition system with multiple space - time channels based on a microcomputer
多時空通道中子注量率密度數據採集系統方案設計 -
A rectangular target with its aspect ratio 2. 5 : 1 gives the higher neutron flux than square target with the same area. for the same shape, the neutron flux increases then turn to decrease with decreasing the area of the target
接下來根據已優化的靶的參數，利用低能粒子輸運程序mcnp4a進一步計算高能中子（快中子）進入慢化器后，在慢化器中的輸運過程。 -
The neutron flux extracted to different angles has been calculated. finally, the heat depositions in the target, the reflector and the moderator have been calculated. based on these results, the temperature and stress distribution hi tungsten target under different cooling condition have been calculated too
最後計算了靶、反射體以及不同慢化器（水、液態氫、液態甲烷）中的熱量沉積，並以此為依據，利用工程軟體ideas進一步計算了各種冷卻條件下，靶中溫度場與應力場分佈。 -
The maximum heating rate of absorber is o. skw. ? h / ? inside experiment fuel rod is much lower than that outside experiment device. influence of absorber movement on thermal neutron flux decreases, as radial distance between absorber and measuring point increases
給出了硼不銹鋼和銀分別做為吸收體的兩種方案的計算結果，即有效增殖因子keff 、中子通量密度分佈、燃料棒功率、吸收體組分及其發熱，並進行了分析、比較，為瞬態試驗裝置的設計提供了參數。 -
At first, the effect of the target on the neutron flux is discussed to determine the optimal proton energy, target material, shape and dimension by using the high - energy particle transport code nmtc / jam
首先利用高能粒子輸運程序nmtc jam計算了入射質子能量、靶的材料、形狀、尺寸以及靶與慢化器耦合對中子通量的影響。 -
When a < 0, move / v to the right side and look upon it as source term. the calculation result shows that the r indirect method can compute deeper than k indirect method in subcritical system. but the y indirect method has no inner iteration, it ca n ' t ensure the convergence of neutron flux and it will also fail in deep subcritical
作參數的嘗試插值法把/分情況處理，當由插值法得到的新值大於零時，仍將/放在輸運方程左端作為吸收項，若0 ，則將其移至右端作為源項處理計算表明，該方法比作參數的嘗試插值法算得的次臨界度深一些，但由於沒有內迭代過程，不能保證通量收斂，在深次臨界情形下同樣會失效。 -
Neutron flux distributions in the reactor core are measured
測量了反應堆堆芯里的中子通量分佈。 -
The method is used to measure the neutron flux distribution in the reactor core
這種方法被用來測量反應堆堆芯的中子通量分佈。 -
Alpha eigenvalue is an characteristic parameter in neutron chain reaction physics. it describes the variational velocity of neutron flux along with time
本徵值是中子鏈式反應物理中表徵系統動態性質的一個重要特徵量，描述中子通量密度隨時間按指數規律變化的快慢。
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