Cold neutron source conceptual designing for Tehran Research Reactor

The purpose of this study is to provide a quick and efficient experimental method to identify and find damaged fuel assemblies (FAs) among all assemblies of the core. This method is based on gamma spectroscopy by measuring the activity ratio of the desired fission fragments that leaked into the coolant. Using the Cs/Cs activity ratio, and considering the history factor for each FA, we determine the fuel burnup. Furthermore, from the I ×I /Xe activity ratio, the power peaking factor can be determined. This spectroscopy is carried out for the Tehran Research Reactor to find its failed FA positions. Then, the spectrum at different cooling times has been studied. Specifically, from the Cs/Cs (0.1212 ± 0.003) activity ratio and the fuel history factor (2.1023), the fuel burnup of damaged fuel is anticipated to be 33.9%, and the result of the computational codes is found to be 33.1%; these two results are consistent with each other. The results of both experiment and code analysis show the relatively reasonable estimation of this method in finding the location of damaged FAs.

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Studies on Production Planning of Dispersion Type U<sub>3</sub>Si<sub>2</sub>-Al Fuel in Plate-Type Fuel Elements for Nuclear Research Reactors

Negro¹,

Durazzo²,

Mesquita³

et al. 2016

WJNST

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Several fuel plants that supply nuclear research reactors need to increase their production capacity in order to meet the growing demand for this kind of nuclear fuel. After the enlargement of the production capacity of such plants, there will be the need of managing the new production level. That level is usually the industrial one, which poses challenges to the managerial staff. Such challenges come from the fact that several of those plants operate today on a laboratorial basis and do not carry inventory. The change to the industrial production pace asks for new actions regarding planning and control. The production process based on the hydrolysis of UF6 is not a frequent production route for nuclear fuel. Production planning and control of the industrial level of fuel production on that production route is a new field of studies. The approach of the paper consists in the creation of a mathematical linear model for minimization of costs. We also carried out a sensitivity analysis of the model. The results help in minimizing costs in different production schemes and show the need of inventory. The mathematical model is dynamic, so that it issues better results if performed monthly. The management team will therefore have a clearer view of the costs and of the new, necessary production and inventory levels.

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Cold neutron source conceptual designing for Tehran Research Reactor

Cited by 3 publications

References 9 publications

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

An efficient method for detecting damaged FAs; burnup and PPF estimations by gamma spectroscopy

Studies on Production Planning of Dispersion Type U<sub>3</sub>Si<sub>2</sub>-Al Fuel in Plate-Type Fuel Elements for Nuclear Research Reactors

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Cold neutron source conceptual designing for Tehran Research Reactor

Cited by 3 publications

References 9 publications

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

An efficient method for detecting damaged FAs; burnup and PPF estimations by gamma spectroscopy

Studies on Production Planning of Dispersion Type U&lt;sub&gt;3&lt;/sub&gt;Si&lt;sub&gt;2&lt;/sub&gt;-Al Fuel in Plate-Type Fuel Elements for Nuclear Research Reactors

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Studies on Production Planning of Dispersion Type U<sub>3</sub>Si<sub>2</sub>-Al Fuel in Plate-Type Fuel Elements for Nuclear Research Reactors