The Tritium System Test Assembly (TSTA) project at Los Alamos National Laboratory is charged with developing and demonstrating the fusion fuel processing requirement for the magnetic fusion energy program. The key fusion fuel streams are the plasma exhaust and the blanket stream. At present, the technology under development at TSTA includes only the plasma exhaust. The blanket is a logical upgrade to TSTA. This possible upgrade is the subject of an ongoing study among LANL, JAERI, and Argonne National Laboratory (ANL). This program, called The Breeding Blanket Interface (BBI), is being investigated with the intention of installing such a processing system at TSTA in the 1992--1993 time frame. The BBI program was initiated in July 1987. The ...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
In the frame of the EUROfusion consortium activities the Helium Cooled Pebble Bed (HCPB) and the Wat...
One of the major requirements for a fusion power plant in the future is tritium self-sufficiency. Fo...
The Tritium Systems Test Assembly (TSTA) at Los Alamos is a full-scale facility dedicated to testing...
The fusion technology development program for tritium in the US is centered around the Tritium Syste...
This document has been prepared for the Major Device Fabrication Review for the Tritium Systems Test...
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate...
The Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory is a facility designed to...
The viability of various materials and blanket designs for use in nuclear fusion reactors can be tes...
The usefulness of ITER to fusion development can be substantially increased if the design parameters...
The Tritium System Test Assembly (TSTA) is a facility built for the demonstration of tritium handlin...
AbstractTritium production is of critical importance to prospective DT fusion power plants. Lithium ...
The principal program objectives for TSTA are: (1) to develop and demonstrate the fuel cycle for fus...
The many possible combinations of blanket materials, tritium generation and recovery systems, and po...
We have initiated a study to define a blanket processing mockup for Tritium Systems Test Assembly. I...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
In the frame of the EUROfusion consortium activities the Helium Cooled Pebble Bed (HCPB) and the Wat...
One of the major requirements for a fusion power plant in the future is tritium self-sufficiency. Fo...
The Tritium Systems Test Assembly (TSTA) at Los Alamos is a full-scale facility dedicated to testing...
The fusion technology development program for tritium in the US is centered around the Tritium Syste...
This document has been prepared for the Major Device Fabrication Review for the Tritium Systems Test...
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate...
The Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory is a facility designed to...
The viability of various materials and blanket designs for use in nuclear fusion reactors can be tes...
The usefulness of ITER to fusion development can be substantially increased if the design parameters...
The Tritium System Test Assembly (TSTA) is a facility built for the demonstration of tritium handlin...
AbstractTritium production is of critical importance to prospective DT fusion power plants. Lithium ...
The principal program objectives for TSTA are: (1) to develop and demonstrate the fuel cycle for fus...
The many possible combinations of blanket materials, tritium generation and recovery systems, and po...
We have initiated a study to define a blanket processing mockup for Tritium Systems Test Assembly. I...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
In the frame of the EUROfusion consortium activities the Helium Cooled Pebble Bed (HCPB) and the Wat...
One of the major requirements for a fusion power plant in the future is tritium self-sufficiency. Fo...