NEUTRONIC FLUX AND POWER DISTRIBUTION IN A NUCLEAR POWER REACTOR USING WIMS-D4 AND CITATION CODES

MAHER N.SARSAM; BASHAIR MOHAMMED SAIED

首页> 外文期刊>International journal of physics and research >NEUTRONIC FLUX AND POWER DISTRIBUTION IN A NUCLEAR POWER REACTOR USING WIMS-D4 AND CITATION CODES

【24h】

NEUTRONIC FLUX AND POWER DISTRIBUTION IN A NUCLEAR POWER REACTOR USING WIMS-D4 AND CITATION CODES

机译：使用WIMS-D4和引用代码的核电反应器中的中子通量和配电

获取原文

获取原文并翻译 | 示例

掌桥外文数据库（机构版） >>

开具论文收录证明 >>

页面导航

摘要
著录项
相似文献
相关主题

摘要

The flux and power distribution of a WWER- 440 nuclear power reactor using CITATION code was calculated. The calculation of the neutronic cross sections values was done using WIMS-D4 code. The comparison between results and benchmark values of the power distributions shows a very good agreement.

机译：计算了使用引文代码的WWER-440核电反应器的通量和功率分布。使用WIMS-D4代码进行中子横截面值的计算。功率分布的结果和基准值之间的比较显示了非常良好的一致性。

著录项

来源
《International journal of physics and research》 |2017年第1期|共16页
作者
MAHER N.SARSAM; BASHAIR MOHAMMED SAIED;
展开▼
作者单位

Alsalam University College Iraq;

Alsalam University College Iraq;

展开▼
收录信息
原文格式 PDF
正文语种 eng
中图分类物理学;
关键词
distribution; power; cross;

机译：分布;权力;十字架;
入库时间 2022-08-20 02:14:50

相似文献

外文文献
中文文献
专利

1. NEUTRONIC FLUX AND POWER DISTRIBUTION IN A NUCLEAR POWER REACTOR USING WIMS-D4 AND CITATION CODES [J] . MAHER N.SARSAM, BASHAIR MOHAMMED SAIED International journal of physics and research . 2017,第1期

机译：使用WIMS-D4和引用代码的核电反应器中的中子通量和配电
2. Benchmark evaluation of reactor critical parameters and neutron fluxes distributions at zero power for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP [J] . A. Borio di Tigliole, A. Cammi, M. Clemenza, Progress in nuclear engergy . 2010,第5期

机译：使用蒙特卡罗代码MCNP对帕维亚大学TRIGA Mark II反应堆在零功率下的反应堆关键参数和中子通量分布进行基准评估
3. Procedure of Calculation of the Spatial Distribution of Temperatures and Heat Fluxes in the Steam Generator of a Nuclear Power Installation with an RBEC Fast-Neutron Reactor [J] . A. A. Frolov, A. A. Sedov Thermal engineering . 2016,第8期

机译：带有RBEC快中子反应堆的核动力装置蒸汽发生器中温度和热通量的空间分布计算程序
4. NEUTRON FLUX DISTRIBUTION INSIDE THE CILINDRICAL CORE OF MINOR EXCESS OF REACTIVITY IN THE IPEN/MB-01 REACTOR AND COMPARISON WITH CITATION CODE AND MCNP-5 CODE [C] . Vitor O. G. Aredes, Ulysses dUtra Bitelli, Luiz E. C. Mura, International Nuclear Atlantic Conference . 2018

机译：中子通量分布在IPEN / MB-01反应器中少量反应性的圆柱核心内部，与引文码和MCNP-5代码的比较
5. STUDIES IN NUCLEAR POWER REACTOR OPERATIONS: I. OPTIMISATION OF RADIAL POISON DISTRIBUTION DURING FIXED FUEL OPERATION. II. CASH-FLOW STUDIES OF POWER REACTOR OPERATIONS UNDER TIME-VARYING, NON-EQUILIBRIUM MARKET CONDITIONS. [D] . COATES, DAVID EWING. 1968

机译：核动力堆运行的研究：I.固定燃料运行过程中径向毒物分布的优化。二。时变，非平衡市场条件下电抗器操作的现金流研究。
6. Power laws in citation distributions: evidence from Scopus [O] . Michal Brzezinski -1

机译：引文分布中的幂律：Scopus的证据
7. MODIFICATIONS TO THE MONTE CARLO CODES USED TO CALCULATE POWER DISTRIBUTION AND NEUTRON LEAKAGE FROM THE TSF--SNAP REACTOR. [O] . K.D. Franz, V.R. Cain 1969

机译：修改用于计算TSF - 快照反应器的功率分布和中子泄漏的蒙特卡罗代码。
8. Computer Program for Determining the Space Distribution of the Temperature and of the Density in the Thermonuclear Plasma of a Power Thermonuclear Reactor Controlled by the Neutron Nuclear Reactions Rate, Code DSTD-2 [R] . Christea, G. 1976

机译：确定中子核反应速率控制的功率热核反应堆温度和密度的空间分布的计算机程序，代码DsTD-2

NEUTRONIC FLUX AND POWER DISTRIBUTION IN A NUCLEAR POWER REACTOR USING WIMS-D4 AND CITATION CODES

摘要

著录项

相似文献

相关主题

期刊订阅