In the conversion of fuel in the Tehran Research Reactor core from Highly- Enriched Uraniutn to Low-Enriched Uranium fuel neutronics analysis, thermal hydraulic calculations and kinetic performance of the core have to be studied. In this study, static and dynamic core performance for HEU and LEU fuels were investigated. In static conditions, two groups of neutron flux distributions in axia...

An accurate description of the fluid flow and heat transfer within a Pressurized Water Reactor (PWR), for the safety analysis and reactor performance is always desirable. In this paper a mathematical model of the fundamental physical phenomena which are associated to a typical PWR is presented. The mathematical model governs the fluid dynamics in the reactor. Using commercial software CFX, a co...

the basic structure of a reactor physics laboratory environment simulation software, developed using object modeling technique (omt), and based on the reactor point kinetic equation, is presented. also, various capabilities of the simulator in teaching the fundamental concepts of reactor physics are discussed. in this virtual laboratory, student can perform seven different experiments, namely, ...

This paper analyzes the power loss of magnetically controlled reactor based on the basic theory of the electromagnetic field. In a variety of magnetic valve structure model as the object, physical simulation models of the reactor are built. Using Ansoft Maxwell simulation software, various magnetic valve structures of the reactor are studied by the analysis of the magnetic valve type reactor co...

The present work investigates an appropriate way to calculate the 1700 atomic density changes in the reactor operations. To automate this procedure, a computer program has been designed by C#. This program suggests a way to solve this problem which is based on the solution system of differential equations (Bitman) that it is designed according to Runge-Kutta Fehlberg method. The designed softwa...

The paper investigates parallel channel instabilities of natural circulation boiling water reactor. A thermal-hydraulic model is developed to simulate two-phase flow behavior in the natural circulation boiling water reactor (NCBWR) with the incorporation of ex-core components and recirculation loop such as steam separator, down-comer, lower-horizontal section and upper-horizontal section and th...

This problem is known as the Lambda Modes problem. The fundamental eigenvalue (the largest one) is called the effective multiplication, k-effective, of the reactor core. This eigenvalue and its corresponding eigenfunction describe the steady state neutron distribution in the core. On the other hand, to compute the dominant modes of the reactor core is useful to develop modal methods [2] to inte...

The basic structure of a reactor physics laboratory environment simulation software, developed using object modeling technique (OMT), and based on the reactor point kinetic equation, is presented. Also, various capabilities of the simulator in teaching the fundamental concepts of reactor physics are discussed. In this virtual laboratory, student can perform seven different experiments, ...

The MELCOR Core (COR) package calculates the thermal response of the core and lower plenum internal structures, including the portion of the lower head directly below the core. The package also models the relocation of core and lower plenum structural materials during melting, slumping, and debris formation, including failure of the reactor vessel and ejection of debris into the reactor cavity....