The basis processes for reprocessing thorium based light water reactor type fuels are defined for use in identifying criticality data needs. The Reference Thorium Fuel Cycle is used as the primary fuel cycle. Material forms and compositions are described for each major processing step. These forms consist of nitrates and oxides of Th--U--Pu combinations. Fuel fabrication and fuel pool storage facilities are also defined to the extent they interact with fuel reprocessing
The molten salt reactor is one of the six concepts retained by the Generation IV forum in 2001. Base...
The purpose of this paper is to present a brief description of fuel reprocessing and some present de...
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...
A number of fuel cycles have been proposed for evaluation in the nonproliferation alternative system...
Thorium, which is a fissile nuclide, was considered as a fuel for nuclear power plants in the beginn...
This paper is an attempt to assess and review the materials aspects of the thorium fuel cycle. It st...
The use of thorium as a “fertile” material in combination with a fissile material (either U233, U235...
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an...
This book presents the state of the art on thermophysical and thermochemical properties, fabrication...
This publication continues the quarterly series presenting results of work performed under the Natio...
This report describes the fabrication of proliferation-resistant thorium oxide/uranium oxide ceramic...
Data on thorium are compiled and the use of thorium as a fuel material is discussed. It was assumed ...
Thorium-containing nuclear fuel is proposed as a means of gaining a number of benefits in the operat...
The use of thorium in combination with plutonium in nuclear power generation offers a solution to th...
The molten salt reactor is one of the six concepts retained by the Generation IV forum in 2001. Base...
The purpose of this paper is to present a brief description of fuel reprocessing and some present de...
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...
A number of fuel cycles have been proposed for evaluation in the nonproliferation alternative system...
Thorium, which is a fissile nuclide, was considered as a fuel for nuclear power plants in the beginn...
This paper is an attempt to assess and review the materials aspects of the thorium fuel cycle. It st...
The use of thorium as a “fertile” material in combination with a fissile material (either U233, U235...
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an...
This book presents the state of the art on thermophysical and thermochemical properties, fabrication...
This publication continues the quarterly series presenting results of work performed under the Natio...
This report describes the fabrication of proliferation-resistant thorium oxide/uranium oxide ceramic...
Data on thorium are compiled and the use of thorium as a fuel material is discussed. It was assumed ...
Thorium-containing nuclear fuel is proposed as a means of gaining a number of benefits in the operat...
The use of thorium in combination with plutonium in nuclear power generation offers a solution to th...
The molten salt reactor is one of the six concepts retained by the Generation IV forum in 2001. Base...
The purpose of this paper is to present a brief description of fuel reprocessing and some present de...
Voloxidation and dissolution studies: rotary-kiln heat-transfer tests are under way using a small ro...