A Coupled Point Kinetics Neutronics and Thermal-fluid Model for Pebble Bed Gas-cooled Reactors

A Coupled Point Kinetics Neutronics and Thermal-fluid Model for Pebble Bed Gas-cooled Reactors
Title A Coupled Point Kinetics Neutronics and Thermal-fluid Model for Pebble Bed Gas-cooled Reactors PDF eBook
Author Leon Cillie Malan
Publisher
Pages 112
Release 2009
Genre
ISBN

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Coupled Neutronics and Thermal-hydraulics Modeling for Pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR)

Coupled Neutronics and Thermal-hydraulics Modeling for Pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR)
Title Coupled Neutronics and Thermal-hydraulics Modeling for Pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) PDF eBook
Author Xin Wang
Publisher
Pages 136
Release 2018
Genre
ISBN

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Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor

Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor
Title Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor PDF eBook
Author Brian Boer
Publisher
Pages 0
Release 2008
Genre Nuclear fuels
ISBN 9781586039660

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The Very High Temperature Reactor (VHTR) has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. As one of the fourth generation nuclear reactors, the VHTR is characterized by high plant efficiency and a high fuel discharge burn-up level. More specifically, the (pebble-bed type) High Temperature Reactor (HTR) is known for its inherently safe characteristics, coming from a negative temperature reactivity feedback, a low power density and a large thermal inertia of the core.

Proceedings of the International Conference on the Physics of Nuclear Science and Technology

Proceedings of the International Conference on the Physics of Nuclear Science and Technology
Title Proceedings of the International Conference on the Physics of Nuclear Science and Technology PDF eBook
Author
Publisher
Pages 852
Release 1998
Genre Science
ISBN

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment
Title Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment PDF eBook
Author Jyeshtharaj Joshi
Publisher Woodhead Publishing
Pages 888
Release 2019-06-11
Genre Science
ISBN 0081023375

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology
Title Advances in High Temperature Gas Cooled Reactor Fuel Technology PDF eBook
Author International Atomic Energy Agency
Publisher
Pages 639
Release 2012-06
Genre Business & Economics
ISBN 9789201253101

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This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

NUREG/CR.

NUREG/CR.
Title NUREG/CR. PDF eBook
Author U.S. Nuclear Regulatory Commission
Publisher
Pages 144
Release 1977
Genre Nuclear energy
ISBN

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