This report describes the fabrication of proliferation-resistant thorium oxide/uranium oxide ceramic fuel pellets and preparations at the Savannah River Laboratory (SRL) to irradiate those materials. The materials were fabricated in order to study head end process steps (decladding, tritium removal, and dissolution) which would be required for an irradiated proliferation-resistant thorium based fuel. The thorium based materials were also to be studied to determine their ability to withstand average commercial light water reactor (LWR) irradiation conditions. This program was a portion of the Thorium Fuel Cycle Technology (TFCT) Program, and was coordinated by the Oak Ridge National Laboratory (ORNL) under the Consolidated Fuel Reprocessing ...
The advantages and disadvantages of the use of thorium bearing fuel in light water reactors have be...
A series of preliminary irradiations has been made on ceramic fuels of interest for thermal reactors...
1. Summary Project Objectives: Our objective is to develop a fuel consisting of mixed thorium diox...
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an...
Thorium based fuels are being tested in the Halden Research Reactor in Norway with the aim of produc...
The major results of the Phase 1 (1979 - 1983) of the program "Th-Utilization in PWRs" are presented...
In this irradiation experiment, (Th,Pu)O2 pellets were fabricated from powders, prepared using a sol...
Voloxidation and dissolution studies: rotary-kiln heat-transfer tests are under way using a small ro...
The review reveals that experience in the reprocessing of irradiated thorium materials is limited. P...
Thorium-containing nuclear fuel is proposed as a means of gaining a number of benefits in the operat...
The Lewis Research Center of the National Aeronautics and Space Administration initiated a project a...
Test quantities of thoria (aporoximately 3800 lb of thorium oxide and 3200 lb of mixed thorium-urani...
Detailed investigations performed for a standard 1,300 MW$_{e}$ PWR show that (Th,U)O$_{2}$ and (Th,...
This book presents the state of the art on thermophysical and thermochemical properties, fabrication...
Since the beginning of Nuclear Energy Development, thorium was considered as a potential fuel, mainl...
The advantages and disadvantages of the use of thorium bearing fuel in light water reactors have be...
A series of preliminary irradiations has been made on ceramic fuels of interest for thermal reactors...
1. Summary Project Objectives: Our objective is to develop a fuel consisting of mixed thorium diox...
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an...
Thorium based fuels are being tested in the Halden Research Reactor in Norway with the aim of produc...
The major results of the Phase 1 (1979 - 1983) of the program "Th-Utilization in PWRs" are presented...
In this irradiation experiment, (Th,Pu)O2 pellets were fabricated from powders, prepared using a sol...
Voloxidation and dissolution studies: rotary-kiln heat-transfer tests are under way using a small ro...
The review reveals that experience in the reprocessing of irradiated thorium materials is limited. P...
Thorium-containing nuclear fuel is proposed as a means of gaining a number of benefits in the operat...
The Lewis Research Center of the National Aeronautics and Space Administration initiated a project a...
Test quantities of thoria (aporoximately 3800 lb of thorium oxide and 3200 lb of mixed thorium-urani...
Detailed investigations performed for a standard 1,300 MW$_{e}$ PWR show that (Th,U)O$_{2}$ and (Th,...
This book presents the state of the art on thermophysical and thermochemical properties, fabrication...
Since the beginning of Nuclear Energy Development, thorium was considered as a potential fuel, mainl...
The advantages and disadvantages of the use of thorium bearing fuel in light water reactors have be...
A series of preliminary irradiations has been made on ceramic fuels of interest for thermal reactors...
1. Summary Project Objectives: Our objective is to develop a fuel consisting of mixed thorium diox...