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