neutrontransport crosssection

用法例句

For the numerical solutions of the neutron transport equation based on unstructured- meshes,four types of new methods were developed including the spherical harmonics(P_n)finite element method,the discrete ordinates(S_n)finite element method,the triangle transmission probability method,and the triangle nodal method.

针对非结构网格下中子输运方程的求解方法问题,分别研究了球谐函数(P_n)有限元方法、离散纵标(S_n)有限元方法、三角形穿透概率方法和三角形节块S_n方法的计算模型。

A 3\|D multigroup P\-3 approximation Monte Carlo code MCMG\|BURN is developed by coupling the neutron transport and burnup.

介绍三维多群中子输运 燃耗耦合P3近似蒙特卡罗程序MCMG BURN 。

The phase-space finite element method is applied to the multigroup neutron transport equation in cylindrical critical systems.

本文采用相空间有限元方法求解了柱形临界多群中子输运问题。

neutron data direct access

中子截面数据直接存取

thermal cross section reactor physics computer code

反应堆物理热中子截面计算机代码

Development and Benchmark Validation of Temperature-Dependent Neutron Cross-Section Library for MCNP

MCNP温度相关中子截面库的研制及基准验证

thermal inelastic scattering cross sectio

热中子非弹性散射截面

thermal neutron macroscopic absorption cross section

热中子宏观吸收截面

macroscopic thermal neutron absorption capture cross section

宏观热中子吸收俘获截面

Computer simulation of Poincare section in the study of quantum chaos;

量子混沌研究中Poincare截面的计算机模拟

The Effect of Low Energy Neutrons From Monoenergetic Neutron Source on Activation Cross Section Measurements

单能中子源中低能成份对活化截面测量的影响

Studies on Hydrogen Atom and H_2～+ in Strong Fields and the Photoionization Cross Section of Li～+;

强场中的H原子、H_2～+以及Li～+光吸收截面的研究

Experimental Measurement and Monte Carlo Correction of Neutron Capture Cross-sections;

中子俘获截面的实验测量和蒙特卡罗修正

An Empirical Study of the Explanatory Factors to the Cross-Sectional Expected Returns in China s Stock Market;

中国股市横截面预期收益解释因子的实证研究

Sectional Curvature of Compact Minimal Submanifolds of Locally Symmetric Manifolds;

局部对称空间中的紧致极小子流形的截面曲率

The Fitting of Section-data Within MC Simulating the Transportation of Photons

蒙特卡罗模拟光子输运中截面数据的拟合

(physics) a unit of nuclear cross section.

（物理）原子有效截面单位。

Hooks and the Section of Auslander-Reiten Components;

钩子与Auslander-Reiten分支的截面

The fission barrier parameters for actinide nuclei were obtained by analysis and calculations of fission cross-sections and complete neutron reaction cross sections.

通过分析和计算锕系核裂变截面和全套中子反应截面获取了一组锕系核的裂变位垒参数.

Measurement and Analysis of the Double-differential Cross Sections of Secondary Neutrons for ~9Be at 21.65 MeV Incident Neutrons

21.65MeV中子引起~9Be反应的次级中子双微分截面测量与分析

Measurement of Secondary Neutron Emission Double-Differential Cross Section for Natural Iron Induced by 8.17 MeV Neutron

8.17MeV中子与天然铁作用的次级中子双微分截面测量