MCNP的例句大全

Computing with MCNP the thermal flux density due to the delayed fission neutron generated in processing the clads of burned-up fuel roads

用MCNP程序计算核燃料废包壳缓发裂变中子形成的热中子通量密度

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The work presented in this article is focused on the description of the fast-thermal coupled ADS subcritical reactor core and the calculation of the values of K_ ( eff) using the Monte Carlo code MCNP under various parameters of the reactor core.

文章主要是对快热耦合ADS次临界堆芯进行了描述，利用蒙特卡罗代码MCNP模拟计算一系列不同堆芯参数下的K eff值。

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As to the computation of the components outsides of reactor core, MCNP code is not very reasonable because it is a deep penetration problem.

对于反应堆外围组件的计算，因为它是一个深穿透计算问题，所以采用MCNP程序进行计算不太适合；

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MCNP is a general and powerful Monte Carlo N-Particle transport code, which is widely used in the field of reactor physics radiation protection, nuclear detection, aerospace etc. It has geometrical adaptability, high accuracy on calculation and analysis of nuclear physics.

基于蒙特卡罗方法的粒子输运程序MCNP在进行核物理计算分析时，因具有几何适应性强、计算精度高等众多特点，已广泛应用于反应堆物理、辐射防护、核探测和航空航天等诸多领域。

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Compared with the use of MCNP code, the use of MORSE code has the advantages of smaller size of computer memory, shorter computational time and is more convenient.

应用MORSE程序进行中子测井数值模拟与MCNP等大型程序相比有占用计算机内存少、节省机时和使用方便等优点。

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MCNP is a general-purpose Monte Carlo N-particle code that can be used for neutron, photon, electron, or coupled neutron/ photon/ electron transport.

MCNP是用于计算重子、光子或者中子/电子/输运方程的通用蒙特卡罗中性粒子输运计算程序。

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So, The distributing of the scattering background neutrons in the experiment hall is calculated with the MCNP/ 4A code.

需用MCNP／4A程序计算实验大厅的散射中子本底分布。

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MCNP code is a large multipurpose Monte Carlo code. It can be used for radiation shielding calculation, neutron extraction channel design, and some critical facility design.

MCNP3B程序是一个大型的多功能蒙特卡罗程序，可用于屏蔽设计和应用孔道的设计，以及某些临界装置的设计计算。

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the issue predigests geometric structure of sprr-300 reactor core with repeated structure geometry feature of mcnp code and sets up the irradiation channel mathematical model to calculate the neutron flux.

利用MCNP程序的重复几何结构功能，对SPRR-300的堆芯几何结构进行了简化处理，建立了该堆辐照孔道中子注量率分布计算的数学模型。

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The Dose Distribution of Head for BNCT Based on MCNP

基于MCNP的BNCT人体头部剂量分布计算

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This paper presents the research of the inspection ray of~ ( 60) Co radiography system using MCNP code.

应用MCNP程序研究了60Co大型客体辐射成像系统中的检测射线束。

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Analysis of parallel computing performance of the code MCNP

MCNP程序并行计算性能分析

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Parallelization of MCNP Monte Carlo neutron and photon transport code

蒙特卡罗中子-光子输运程序MCNP的并行化

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The dose-depth distribution in duplicating paper and polystyrene were calculated using a Monte Carlo N-Particle ( MCNP) code to develop a mail sterilization system using radiation from linear electron accelerators.

为研制加速器电子束邮件灭菌安全系统，用Monte Carlo（MCNP）程序模拟计算了4.5MeV电子束辐照复印纸和聚苯乙烯时吸收剂量随深度的变化。

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Dose distributions of BNCT based on Chinese body anatomically characteristics head phantom with MCNP code

MCNP程序计算中国人特性头模BNCT剂量分布

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Research and implementation of an algorithm of converting UG model to MCNP geometry model

一种从UG模型到MCNP几何模型转换算法的研究与实现

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Therefore, MCNP simulated data are credible.

因此，MCNP模拟得到的数据是可信的。

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In-Pile Sample Value Calculation With MCNP Code

基于MCNP程序的入堆样品价值计算

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Application of MCNP Code in Research of Neutron Detecting Technique in Nuclear Warhead Verifying

MCNP程序在核弹头核查中子探测技术研究中的应用

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Requirement of Temperature Dependent Nuclear Cross Sections for MCNP Calculation

温度相关核截面数据库在MCNP计算中的必要性研究

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