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Second International Forum on Expert Systems and Computer Simulation in Energy Engineering
March, 17-20, 1992, Erlangen, Germany

DOI: 10.1615/ICHMT.1992.IntForumExpSysCompSimEE


ISBN Print: 978-1-56700-486-1

MODIFICATION AND DEVELOPMENT OF RESEARCH REACTOR CORE

pages 19.3.1-19.3.5
DOI: 10.1615/ICHMT.1992.IntForumExpSysCompSimEE.720
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RÉSUMÉ

The goal of this work is to choose the best method for up grading research reactor power. Two types of fuel elements were studied: pin type square lattice and IRI-2M fuel assemblies (with the use of beryllium reflector). This paper presents a code developed for core heat transfer calculations of the research reactor up grading through the previously mentioned two types of fuel elements: The results showed that when using IRT-2M fuel assemblies for up grading core, it has inherently stable operating characteristics due to accidental increase in reactivity than that when using the fuel pin type.

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