The cores and reflectors in modem High Temperature Gas Cooled Reactors (HTRs) are constructed from graphite components. There are two main designs; the Pebble Bed design and the Prism design, see Table 1. In both of these designs the graphite not only acts as a moderator, but is also a major structural component that may provide channels for the fuel and coolant gas, channels for control and safety shut off devices and provide thermal and neutron shielding. In addition, graphite components may act as a heat sink or conduction path during reactor trips and transients. During reactor operation, many of the graphite component physical properties are significantly changed by irradiation. These changes lead to the generation of significant inter...
This dissertation focuses on the investigation of the microstructures of two nuclear grade matrix gr...
Experimental data for grade H-451 graphite are presented and assessed to support licensing of H-451 ...
The High Temperature Gas-Cooled Reactor (HTGR) is a Generation IV reactor concept that uses a graphi...
The Next Generation Nuclear Plant (NGNP) will be a helium-cooled High Temperature Gas Reactor (HTGR)...
High-temperature gas-cooled reactor (HTGR) is one of promising candidates for new generation of nucl...
Experimental data on the mechanical properties of reactor graphites (excluding irradiation creep and...
The High-temperature Gas-cooled Reactor (HTGR) is a helium-cooled, graphite-moderated, solid-homogen...
Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor ...
Graphite and graphite composite materials are of great importance in various applications; however, ...
The high temperature gas cooled reactor (HTR) is developing rapidly toward a modular, compact, and i...
The high temperature gas-cooled reactor (HTGR) has potential utilization due to its featured charact...
The objectives of the Graphite Design Handbook (GDH) are to provide and maintain a single source of ...
Graphite is used as a nuclear moderator and a structural material in the core of gas-cooled reactors...
British gas-cooled reactors are graphite-moderated and cooled by CO2. During service, the moderator ...
Prismatic fuel element made of graphite are used in the core of the High-Temperature Gas-Cooled Reac...
This dissertation focuses on the investigation of the microstructures of two nuclear grade matrix gr...
Experimental data for grade H-451 graphite are presented and assessed to support licensing of H-451 ...
The High Temperature Gas-Cooled Reactor (HTGR) is a Generation IV reactor concept that uses a graphi...
The Next Generation Nuclear Plant (NGNP) will be a helium-cooled High Temperature Gas Reactor (HTGR)...
High-temperature gas-cooled reactor (HTGR) is one of promising candidates for new generation of nucl...
Experimental data on the mechanical properties of reactor graphites (excluding irradiation creep and...
The High-temperature Gas-cooled Reactor (HTGR) is a helium-cooled, graphite-moderated, solid-homogen...
Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor ...
Graphite and graphite composite materials are of great importance in various applications; however, ...
The high temperature gas cooled reactor (HTR) is developing rapidly toward a modular, compact, and i...
The high temperature gas-cooled reactor (HTGR) has potential utilization due to its featured charact...
The objectives of the Graphite Design Handbook (GDH) are to provide and maintain a single source of ...
Graphite is used as a nuclear moderator and a structural material in the core of gas-cooled reactors...
British gas-cooled reactors are graphite-moderated and cooled by CO2. During service, the moderator ...
Prismatic fuel element made of graphite are used in the core of the High-Temperature Gas-Cooled Reac...
This dissertation focuses on the investigation of the microstructures of two nuclear grade matrix gr...
Experimental data for grade H-451 graphite are presented and assessed to support licensing of H-451 ...
The High Temperature Gas-Cooled Reactor (HTGR) is a Generation IV reactor concept that uses a graphi...