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Simulation Program of the Nuclear Reactor Core with WIMS and COBRA Source Code and Solution to Dynamic Equations by Finite Element Method

机译：WIMS和COBRA源代码的核反应堆堆芯仿真程序以及有限元法求解动力方程

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入库时间 2022-08-26 14:11:32

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1. Reactivity coefficients simulation of the Iranian VVER-1000 nuclear reactor using WIMS and CITATION codes [J] . F. Faghihi, A.H. Fadaie, R. Sayareh Progress in Nuclear Energy . 2007,第1期

机译：使用WIMS和CITATION代码模拟伊朗VVER-1000核反应堆的反应系数
2. Solution of parabolic equations by backward Euler-mixed finite element methods on a dynamically changing mesh [J] . Dawson C., Kirby R. SIAM Journal on Numerical Analysis . 2000,第2期

机译：动态变化网格上倒向Euler混合有限元方法求解抛物线方程
3. Source codes and simulation data for the finite element implementation of the conventional and localizing gradient damage methods in ABAQUS [J] . Subrato Sarkar, I.V. Singh, B.K. Mishra, Data in Brief . 2019,第1期

机译：ABAQUS中常规和局部梯度损伤方法的有限元实现的源代码和仿真数据
4. SIMULATION PROGRAM OF THE NUCLEAR REACTOR CORE WITH WIMS AND COBRA SOURCE CODE AND SOLUTION TO DYNAMIC EQUATIONS BY FINITE ELEMENT METHOD [C] . Hojabri Alireza, Vaziri Nima, Ghoranneviss Mahmood, International Conference on Nuclear Engineering . 2005

机译：用WIMS和COBRA源代码的核反应堆核心仿真程序和通过有限元方法对动态方程的解决方案
5. Development and implementation of a finite element solution of the coupled neutron transport and thermoelastic equations governing the behavior of small nuclear assemblies [D] . Wilson, Stephen Christian 2006

机译：中子输运与热弹性方程耦合控制小型核组件行为的有限元解的开发与实现
6. Source codes and simulation data for the finite element implementation of the conventional and localizing gradient damage methods in ABAQUS [O] . Subrato Sarkar, I.V. Singh, B.K. Mishra, 2019

机译：ABAQUS中常规和局部梯度损伤方法的有限元实现的源代码和仿真数据
7. Effective methods for solution of nonlinear reactor dynamics problems using finite elements. [O] . Olsen Richard Allen 1975

机译：解决有限元非线性反应堆动力学问题的有效方法。
8. COBRA-NC: A Thermal Hydraulics Code for Transient Analysis of Nuclear Reactor Components. Volume 2. COBRA-NC Numerical Solution Methods. [R] . Thurgood, M. J., George, T. L., Wheeler, C. L. 1986

机译：COBRa-NC：核反应堆组件瞬态分析的热工水力学规范。第2卷.COBRa-NC数值解法。

Simulation Program of the Nuclear Reactor Core with WIMS and COBRA Source Code and Solution to Dynamic Equations by Finite Element Method

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