Thermomecanics of fuel for pressurized water reactors
Article REF: BN3060 V1

Thermomecanics of fuel for pressurized water reactors

Authors : Patrick BLANPAIN, Christophe GARNIER, Pierre IMBERT, Hubert SALAUN

Publication date: July 10, 2011 | Lire en français

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Overview

ABSTRACT

Thermomechanics of fuel consists in studying the mechanical and thermal effects but mostly the behavior of the fuel assembly and rod when placed inside the reactor. This article also presents the hydraulic and chemical stresses as well as the phenomena induced by materials irradiation. It furthermore mentions the studies on fuel assembly behavior firstly in normal operating mode and then in incidental and accidental conditions. Although they cannot be described precisely the principles of the used methodology are nonetheless mentioned.

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AUTHORS

  • Patrick BLANPAIN: PhD Chemistry-Physics - International Expert AREVA NP, Fuel, France

  • Christophe GARNIER: Doctorate in Mechanical Engineering - AREVA NP expert, Fuel, France

  • Pierre IMBERT: Doctorate in Fluid Mechanics - AREVA NP Expert, Head of Thermohydraulic Fuel Department, France

  • Hubert SALAUN: Mechanical engineer - AREVA NP Expert, Assembly mechanics, Fuel, France

 INTRODUCTION

Fuel thermomechanics refers to studies of the mechanical and thermal effects and, more generally, to studies of the behavior of fuel assemblies and rods under the various stresses to which they are subjected in reactors, including thermal and mechanical loads, hydraulic and chemical stresses and phenomena induced by irradiation of materials.

In this chapter, we describe the studies carried out on the behavior of the fuel assembly, first under normal operating conditions, then under incidental and accidental conditions. It is not possible here to give precise numerical descriptions of all the models used to carry out these studies. However, we will describe the principles of the methodology and the main models used.

For a description of the PWR fuel assembly and general operating conditions, please refer to the PWR articles in this treatise.

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Thermomechanics of pressurized water reactor fuel

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