Operational experience at the SRE and evaluation of alternate methods resulted in the development of an optimized fuel-handling system for the Hallam Nuclear Power Facility Beactor. Increased reliability, easier maintenance, improved safeguards, and broader flexibility are some of the characteristics of this system, which features a manually-operated, shielded cask with reactor atmosphere seals that is usable in a conventional unshielded air-atmosphere building. (auth
The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-c...
Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the applicatio...
This work addresses the neutronic performance and criticality safety issues of transport casks for f...
The Sodium Reactor Experiment (SRE) was constructed to demonstrate the feasibility of sodium-oooled ...
The reactor refuelling system provides the means of transporting, storing, and handling reactor core...
Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fu...
This work focuses on the design, improvements, and manufacturing of a new fuel handling tool for the...
The results of an investigation to integrate a Na/sup 24/ irradiation processing facility with an op...
The major design features, nuclear characteristics and performance data for a nuclear fueled central...
The means used to prevent the recurrence of tetralin leakage into the SRE sodium systems are discuss...
A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, ...
The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summar...
The effect of fuel programming, i.e., the scheme used for changing fuel in a core, on the reactivity...
Small graphite-moderated and gas-cooled reactors have been around since the beginning of the atomic ...
An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-p...
The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-c...
Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the applicatio...
This work addresses the neutronic performance and criticality safety issues of transport casks for f...
The Sodium Reactor Experiment (SRE) was constructed to demonstrate the feasibility of sodium-oooled ...
The reactor refuelling system provides the means of transporting, storing, and handling reactor core...
Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fu...
This work focuses on the design, improvements, and manufacturing of a new fuel handling tool for the...
The results of an investigation to integrate a Na/sup 24/ irradiation processing facility with an op...
The major design features, nuclear characteristics and performance data for a nuclear fueled central...
The means used to prevent the recurrence of tetralin leakage into the SRE sodium systems are discuss...
A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, ...
The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summar...
The effect of fuel programming, i.e., the scheme used for changing fuel in a core, on the reactivity...
Small graphite-moderated and gas-cooled reactors have been around since the beginning of the atomic ...
An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-p...
The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-c...
Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the applicatio...
This work addresses the neutronic performance and criticality safety issues of transport casks for f...