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DEVELOPMENT AND PRELIMINARY VERIFICATION OF THE 3D CORE NEUTRONIC CODE: COCO

机译:3D核中子代码:COCO的开发和初步验证

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As the recent blooming economic growth and following environmental concerns, China is proactively pushing forward nuclear power development and encouraging the tapping of clean energy. Under this situation, CGNPC, as one of the largest energy enterprises in China, is planning to develop its own nuclear related technology in order to support more and more nuclear plants either under construction or being operation. This paper introduces the recent progress in software development for CGNPC. The focus is placed on the physical models and preliminary verification results during the recent development of the 3D COre Neutronic COde: COCO. In the COCO code, the non-linear Green's function method is employed to calculate the neutron flux. In order to use the discontinuity factor, the Neumann (second kind) boundary condition is utilized in the Green's function nodal method. Additionally, the COCO code also includes the necessary physical models, e.g. single-channel thermal-hydraulic module, burnup module, pin power reconstruction module and cross-section interpolation module. The preliminary verification result shows that the COCO code is sufficient for reactor core design and analysis for pressurized water reactor (PWR).
机译:随着近期经济增长的蓬勃发展以及对环境的关注,中国正在积极推动核电发展,并鼓励开发清洁能源。在这种情况下,作为中国最大的能源企业之一,中广核计划开发自己的核相关技术,以支持越来越多的在建或运营中的核电站。本文介绍了CGNPC软件开发的最新进展。在3D COre Neutronic COde:COCO的最新开发过程中,重点放在物理模型和初步验证结果上。在COCO代码中,采用非线性格林函数方法来计算中子通量。为了使用不连续性因子,格林函数节点法中使用了诺伊曼(第二类)边界条件。另外,COCO代码还包括必要的物理模型,例如单通道热工液压模块,燃耗模块,引脚功率重构模块和横截面插值模块。初步验证结果表明,COCO代码足以用于压水堆(PWR)的堆芯设计和分析。

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