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NEW COMPACT CORE MODEL AND OPTIMUM FUEL LOADING FOR RESEARCH REACTORS AND PROPOSED APPLICATION FOR ANSHAAS REACTOR

E. M. Elsherrbiny
Reactor Department, Nuclear Research Center. Inshaas. EGYPT

Sinopsis

In this work a general model is developed which has a main objective performed through both core model as well as optimum in-core nuclear fuel management for research reactors. The major developed objective is the maximum activation flux that can be obtained with the lowest fuel cost. This goal has been performed during an analytical study of research reactors core design and operation. The core calculation model developed is a three-dimensional, multi-group, diffusion theory and finite difference technique. The significant results of this study is the development of an improved core configuration and refueling scheme for homogeneous research reactors. Many other objectives are performed in a consistent form leading to safe reactor operation. These objectives are: (i) highest extraction burnup achievable, i.e. most economic fuel utilization, (ii) most efficient neutron usage and, (iii) highest core reactivity for any amount of in-core fuel inventory. which is closely related to minimum critical mass.
An applicable objective of this work is to improve the present Anshaas reactor core performance, ETRR-1. A proposed new core model and an optimum fuel loading pattern could be performed with the lowest fuel cost. An addition of irradiation volume of 25mm × 25mm × 500mm with a highest flux obtainable,3.21×1013 neutron/cm2.sec. could be achieved as a flux trap as well as maximum built-in excess reactivity could be gained. Another addition of three irradiation channels each of volume 25mm × 25mm × 500mm with maximum thermal flux 2.83 × 1013 neutrons/cm2.sec. in positions of high importance within a compact core, i.e. with the lowest core fuel inventory, could be achieved. This study has also solved a problem which some users were sometimes suffering . This problem is cocerned with the depression of neutron flux inside the core as a whole in spite of reactor operation at its nominal power level.

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