多物理
热工水力学
核工程
中子输运
蒙特卡罗方法
瞬态(计算机编程)
中子
核反应堆
有限元法
中子通量
研究堆
计算机科学
物理
统计物理学
机械
核物理学
传热
工程类
数学
热力学
统计
操作系统
出处
期刊:International Journal of Radiation Applications and Instrumentation. Part A. Applied Radiation and Isotopes
[Elsevier]
日期:1986-01-01
卷期号:37 (1): 79-80
被引量:130
标识
DOI:10.1016/0883-2889(86)90215-7
摘要
This paper presents a multi-physics and time-dependent model for single-channel transient analysis of a Lead Fast Reactor (LFR). The work focuses on the coupling among the neutronic, the thermal-elastic and the fluid-dynamic phenomena in the considered reactor channel, benefiting from a finite-element scheme of analysis that is implemented in the same simulation environment (COMSOL Multiphysics®), and within a computational domain featured by a moving mesh. A purpose-made six-group neutron diffusion model is developed, which allows to take into account the local dependency of the neutron macroscopic cross-sections on the temperature and density fields. The potential of the multi-physics model to estimate the effective neutron multiplication factor, by means of a comparison with the Monte Carlo code SERPENT, is assessed. A special attention is given to the capability to implicitly catch the thermal-hydraulic and thermal-expansion feedbacks on reactivity, without relying on cross-sections corrective factors. The proposed multi-physics model is employed to investigate the active-core average conditions of the ELSY (European Lead cooled System) reactor, both in steady-state operation and during two transient scenarios. It is shown that the presented model represents a suitable simulation tool for a preliminary investigation of the LFR dynamics, and allows to simultaneously evaluate a wide set of the reactor channel parameters.
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