Simulation program of the nuclear reactor core with WIMS and cobra source code and solution to dynamic equations by finite element method
- 1. Dept. of Physics Karaj Branch, I.Azad University (Iran, Islamic Republic of)
- 2. Plasma Physics Research Center Sciences and Researches Campus, I.Azad University (Iran, Islamic Republic of)
Description
FERKS (Finite Element Reactor Kinetic Simulation) software is utilized for basic design and simulation of the nuclear fission reactor core. This program is incorporated to three main components: Cell design: This module is implemented using WIMS. This code can calculate cross sections, cell layout and eigenvalue in 2-D coordinates. Thermohydrolic design: This Module is implemented using COBRA. Thermohydrolic module computes Thermohydrolic quantities in steady state and transient mode. Dynamic design: This module computes dynamic mode using FERK source code. The solution is based on one unit input of excess reactivity and result of compute of finite elements method in 2-D with temperature feedback and effect of xenon. The region of the core is homogenous circle. The differential equations are transformed to a system of stiff ordinary by Galerkin formulation. Inputs are cross sections, basic thermodynamic properties and geometry of cell. Outputs are flux, temperature and other important quantities. In addition, this module is capable to simulate the motion of control rod with negative input reactivity on element. FERKS application runs on WINDOWS Operating Systems and all the outputs are shown in diagrams. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 7-5022-3400-4
- Imprint Title
- The 13th international conference on nuclear engineering abstracts
- Imprint Pagination
- 604 p.
- Journal Page Range
- p. 597
Conference
- Title
- 13. international conference on nuclear engineering
- Dates
- 16-20 May 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 38014065
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; COORDINATES; CROSS SECTIONS; DIFFERENTIAL EQUATIONS; EIGENVALUES; FEEDBACK; FINITE ELEMENT METHOD; REACTIVITY; REACTOR CORES; STEADY-STATE CONDITIONS; THERMODYNAMIC PROPERTIES; XENON
- Descriptors DEC
- CALCULATION METHODS; ELEMENTS; EQUATIONS; FLUIDS; GASES; MATHEMATICAL SOLUTIONS; NONMETALS; NUMERICAL SOLUTION; PHYSICAL PROPERTIES; RARE GASES; REACTOR COMPONENTS; SIMULATION