Category Archives: Thoria-based Nuclear Fuels

Studies on ThO2

In India, ThO2 has been extensively used in PHWRs for neutron flux flattening of the initial core during start-up. During the last few years, ThO2 bundles have been utilized for this purpose in seven units of PHWR 220 including the two units each at Kakrapar Atomic Power Station (KAPS 1&2), Kaiga Atomic Power Station (KGS 1&2), Rajasthan Atomic Power Station […]

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Thoria-based Nuclear Fuels

It is now amply clear that nuclear energy can be a sustainable source of clean energy for the whole world if we take into account both the fissile and the fertile material resources availability. If, however, uranium-235 is taken as the only fissionable nuclide from which we can generate nuclear power, the exploitable resources are not adequate to supply fuel […]

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Preface

In nuclear power generation establishing the performance of a fuel calls for collective effort of scientists and technologists for addressing various issues of front and back ends of the fuel cycle. These issues pertain to all the operational aspects for smooth functioning right from fuel resourcing, mining and purification, fuel pin fabrication, reactor irradiation, fuel reprocessing, and management of radioactive […]

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ThO2-UO2

Substitution of uranium for thorium in ThO2-UO2 system results in the decrease of lattice parameter, melting point, oxygen potential, thermal conductivity, while the density and the linear thermal expansion show an increase. In the uranium con­centration range y > 0.2, less data are available but the same trend is expected. It was mentioned earlier that, at room temperature, the lattice […]

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Introduction

D. Das This book is introduced with a brief overview of worldwide efforts and recent outlook on the use of thoria-based fuels for power generation. It also summarizes the merits of thoria-based fuels, issues in the thorium fuel cycle, and the past to present accounts of work on the fuels. As preamble to different chapters of the book, reader’s attention […]

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ThO2-PuO2

ThO2 and PuO2 form a continuous series of solid solutions over the entire range of composition. At the Pu-rich end, mixed oxide may be heterogeneous if prepared under reducing conditions, as a result of the formation of Pu2O3. The lattice parameter of (Th1-yPuy)O2 decreases linearly from pure ThO2 to pure PuO2 [26]. Lattice parameters of (Th, Pu)O2 with various PuO2 […]

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Thermophysical Properties of Thoria-based Fuels

T. R. Govindan Kutty, Joydipta Banerjee and Arun Kumar Abstract The behavior of nuclear fuel during irradiation is largely dependent on its thermophysical properties and their change with temperature and burnup. Experi­mental data on out-of-pile properties such as melting point, density, thermal con­ductivity, and thermal expansion are required for fuel design, performance modeling, and safety analysis. The variables that influence […]

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Melting Point

A very important thermophysical property to be considered for an engineering material, like nuclear fuel, is its melting point. The onset of melting at the cen­terline of the fuel rod has been widely accepted as an upper limit to the allowable thermal rating of nuclear fuel elements [11, 12]. The melting point must be taken into account when considering a […]

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