An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that it has very high tritium solubility and results in very low levels of tritium permeation throughout the facility infrastructure. However, lithium metal vigorously reacts with air and water and presents plant safety concerns. The Lawrence Livermore National Laboratory is carrying an effort to develop a lithium-based ternary alloy that maintains the beneficial properties of lithium (e.g. high tritium breeding and solubility) and at the same time reduces overall flammability concerns. This study evaluates the neutronics performance of lithium-based alloys in the blanket of an inertial fusion energy chamber in order to inform such development. 3-...
The tritium breeding and energy absorption in an inertial fusion energy (IFE) reactor chamber have b...
In the frame of the EUROfusion roadmap, the development of a conceptual design for the Demonstration...
The development of a conceptual design for the Demonstration Fusion Power Reactor (DEMO) is a key is...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
The goal of this dissertation is to examine the neutronic properties of a novel type of fusion react...
The goal of this dissertation is to examine the neutronic properties of a novel type of fusion react...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
1 The main objective of this study is to compare the effect of the natural lithium and lithium with ...
17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Ista...
Among the concepts considered in the Advanced Power Extraction (APEX) study is the He-cooled refract...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
In the frame of the EUROfusion roadmap, the development of a conceptual design for the Demonstration...
In the frame of the EUROfusion roadmap, the development of a conceptual design for the Demonstration...
The tritium breeding and energy absorption in an inertial fusion energy (IFE) reactor chamber have b...
In the frame of the EUROfusion roadmap, the development of a conceptual design for the Demonstration...
The development of a conceptual design for the Demonstration Fusion Power Reactor (DEMO) is a key is...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
The goal of this dissertation is to examine the neutronic properties of a novel type of fusion react...
The goal of this dissertation is to examine the neutronic properties of a novel type of fusion react...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage ...
1 The main objective of this study is to compare the effect of the natural lithium and lithium with ...
17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Ista...
Among the concepts considered in the Advanced Power Extraction (APEX) study is the He-cooled refract...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
In the frame of the EUROfusion roadmap, the development of a conceptual design for the Demonstration...
In the frame of the EUROfusion roadmap, the development of a conceptual design for the Demonstration...
The tritium breeding and energy absorption in an inertial fusion energy (IFE) reactor chamber have b...
In the frame of the EUROfusion roadmap, the development of a conceptual design for the Demonstration...
The development of a conceptual design for the Demonstration Fusion Power Reactor (DEMO) is a key is...