This is cne of the r-are text books written in the discipline of Nuclear Reactor Analysis, where the author has considered the interests of both scientists and practising engineers, in addition to serving the needs of the academia. The most attractive feature of this book is a balanced treatment of theory and practice of the subject matter. The theoretical foundations of the reactor design methods are explained with simplified definitions and relevant practical illustrations. The author scans through quickly the traditional aspects of the so-called reactor physics and takes the reader through the details of the analytical aspects in a conventional manner. Hcwever, there is a definite departure from the classical method of approach in order to avoid lengthy and repetitive discussions, that are available in many standard text books on reactor physics. The chief departure fran tradition is the priority accorded to the treatment of the energy part of the problems as opposed to the spatial Dart normally devoted to by other authors . A similar unorthodox approach has been applied while dealing with the solution of the various equations by giving priority to computer oriented mrethods as opposed to the classical solutions.

Nuclear reactor analysis

Nuclear forensic science: correlating measurable material parameters to the history of nuclear material.

On the magnetohydrodynamic Al2O3-water nanofluid flow through parallel fins enclosed inside a partially heated hexagonal cavity

Buoyancy driven magnetohydrodynamic hybrid nanofluid flow within a circular enclosure fitted with fins

Comparative analysis of high conversion achievable in thorium-fueled slightly modified CANDU and PWR reactors

The performances of a light water cooled thorium breeder reactor have been investigated. A feasible region of fresh fuel enrichment and moderator to fuel ratio (MFR) is found to satisfy the constrains of criticality, breeding, and negative void coefficient for several burnups of discharged fuel. The equilibrium fuel cycle burnup calculation has been performed which is coupled with the cell calculation. The MFR is changed to investigate its effect to the breeding capability and void reactivity coefficient profile for different average discharged burnups. For moderated cases, the conversion ratio (CR) decreases with increasing burnup and MFR. The ratio of fissile inventory in equilibrium core to the initial fissile loading (FIR) has the maximum value at certain burnups depending on the MFR and its value increases with the decreasing MFR. Considering to the breeding capability of the reactor, for burnups of equal to 30 GWd/t or higher, the MFR ≤ 0.3 is needed. For the larger MFR and lower burnups, the void r...

https://www.tandfonline.com/doi/pdf/10.1080/18811248.2007.9711334

Feasible Region of Design Parameters for Water Cooled Thorium Breeder Reactor

Impact of different moderator ratios with light and heavy water cooled reactors in equilibrium states

Preliminary study on feasibility of large and small water cooled thorium breeder reactor in equilibrium states

The fuel breeding and void reactivity coefficient of thorium reactors have been investigated using heavy water as coolant for several parametric surveys on moderator-to-fuel ratio (MFR) and burnup. The equilibrium fuel cycle burnup calculation has been performed, which is coupled with the cell calcu- lation for this evaluation. Theof 233 U shows its superiority over other fissile nuclides in the surveyed MFR ranges and always stays higher than 2.1, which indicates that the reactor has a breeding condition for a wide range of MFR. A breeding condition with a burnup comparable to that of a standard PWR or higher can be achieved by adopting a larger pin gap (1-6 mm), and a pin gap of about 2 mm can be used to achieve a breeding ratio (BR) of 1.1. A feasible design region of the reactors, which fulfills the breeding condition and negative void reactivity coefficient, has been found. A heavy-water-cooled PWR-type Th- 233 U fuel reactor can be designed as a breeder reactor with negative void coefficient.

https://www.tandfonline.com/doi/pdf/10.1080/18811248.2008.9711457

Sidik Permana

Papers

Feasible Region of Design Parameters for Water Cooled Thorium Breeder Reactor

Impact of different moderator ratios with light and heavy water cooled reactors in equilibrium states

Preliminary study on feasibility of large and small water cooled thorium breeder reactor in equilibrium states

Breeding Capability and Void Reactivity Analysis of Heavy-Water-Cooled Thorium Reactor

Preliminary study on plutonium and minor actinides utilization in thorims-nes minifuji reactor