In support of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) has performed independent analyses of two advanced Liquid Metal Reactor (LMR) concepts. The designs, sponsored by the US Department of Energy (DOE), the Power Reactor Inherently Safe Module (PRISM) (Berglund, 1987) and the Sodium Advanced Fast Reactor (SAFR) (Baumeister, 1987), were developed primarily by General Electric (GE) and Rockwell International (RI), respectively. Technical support was provided to DOE, RI, and GE, by the Argonne National Laboratory (ANL), particularly with respect to the characteristics of the metal fuels. There are several examples in both PRISM and SAFR where inherent or passive systems provide for a safe response to of...
The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sp...
The long-term vision of a sustainable nuclear energy system is an important driver for the developme...
Molten Salt Reactors (MSR) with the fuel dissolved in the liquid salt and fluoride-salt-cooled High ...
Analyses of the PRISM and SAFR Liquid Metal Reactors with SSC are discussed from a safety and licens...
The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored ...
Liquid metal cooled nuclear reactors for power generation are receiving new research interest becaus...
The US Liquid Metal Reactor Development Program has been restructured to take advantage of the oppor...
The Small Liquid Metal Cooled Reactor Safety Study documents results from activities conducted under...
In recent years, several small modular reactor (SMR) designs have been developed. These nuclear powe...
The PRISM and SAFR designs, as currently proposed by DOE, are designed for ''inherent'', as opposed ...
AbstractMolten salt reactors (MSRs) have a long history with the first design studies beginning in t...
International audienceThe CNRS has focused R&D e˙orts on the development of a new reactor concept ca...
The Light Water Reactor Sustainability (LWRS) Program was established by the U.S. Department of Ener...
The Advanced LWR Nuclear Fuel Development R&D pathway performs strategic research focused on claddin...
Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on qua...
The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sp...
The long-term vision of a sustainable nuclear energy system is an important driver for the developme...
Molten Salt Reactors (MSR) with the fuel dissolved in the liquid salt and fluoride-salt-cooled High ...
Analyses of the PRISM and SAFR Liquid Metal Reactors with SSC are discussed from a safety and licens...
The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored ...
Liquid metal cooled nuclear reactors for power generation are receiving new research interest becaus...
The US Liquid Metal Reactor Development Program has been restructured to take advantage of the oppor...
The Small Liquid Metal Cooled Reactor Safety Study documents results from activities conducted under...
In recent years, several small modular reactor (SMR) designs have been developed. These nuclear powe...
The PRISM and SAFR designs, as currently proposed by DOE, are designed for ''inherent'', as opposed ...
AbstractMolten salt reactors (MSRs) have a long history with the first design studies beginning in t...
International audienceThe CNRS has focused R&D e˙orts on the development of a new reactor concept ca...
The Light Water Reactor Sustainability (LWRS) Program was established by the U.S. Department of Ener...
The Advanced LWR Nuclear Fuel Development R&D pathway performs strategic research focused on claddin...
Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on qua...
The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sp...
The long-term vision of a sustainable nuclear energy system is an important driver for the developme...
Molten Salt Reactors (MSR) with the fuel dissolved in the liquid salt and fluoride-salt-cooled High ...