«New atomic energy technologies» federal program is being realized in Russia. This program includes experimental energy complex development and building, which contains: - a natural safety lead coolant fast reactor «BREST-300»; - a spent fuel recycle facility including fuel fabrication and re-fabrication, radioactive waste immobilization and discarding in accordance with radioactively-equivalent state. The current recycle facility preliminary design involves dry operation of spent fuel elements disassembly using steel shell dissolution by liquid zinc. Fuel element shells are made of special radiation-proof steel «EP-823» containing the following amounts of elements (%): C - 0.2; Мn - 0.8; Si - 1; S - 0.01; Р - 0.015; Сr - 12; Ni - 0.5; Мо -...
An electrometallurgical treatment process has been developed by Argonne National Laboratory to conve...
A physico-chemical model of zinc recovery, in the melt ideal mixing regime, has been developed. From...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
With many nuclear reactors and facilities being decommissioned in the next ten to twenty years the c...
Nuclear operations have resulted in the accumulation of large quantities of contaminated metallic wa...
As the number of nuclear installations undergoing decontamination and decommissioning (D&D) increase...
Recycle of radioactive scrap metals (RSM) from decommissioning of DOE uranium enrichment and nuclear...
The operation and, particularly, the decommissioning of Nuclear Powere Plants (NPPs) and radiochemic...
At the present time the primary problem in a closed nuclear fuel cycle is the management of high lev...
The following presentation is an update to a previous annotation, i.e., WINCO-1138. The literature s...
ABSTRACT Nuclear operations have resulted in the accumulation of large quantities of contaminated me...
The behavior of heavy metals and radionuclides during high-temperature treatment is very important f...
The Research Objectives of this project are to characterize and optimize the use of molten slags to ...
To consolidate metallic waste that is residual from Argonne National Laboratory's electrometallurgic...
Treatment of spent Russian fuel using a Melt-Dilute (MD) process is proposed to consolidate fuel ass...
An electrometallurgical treatment process has been developed by Argonne National Laboratory to conve...
A physico-chemical model of zinc recovery, in the melt ideal mixing regime, has been developed. From...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
With many nuclear reactors and facilities being decommissioned in the next ten to twenty years the c...
Nuclear operations have resulted in the accumulation of large quantities of contaminated metallic wa...
As the number of nuclear installations undergoing decontamination and decommissioning (D&D) increase...
Recycle of radioactive scrap metals (RSM) from decommissioning of DOE uranium enrichment and nuclear...
The operation and, particularly, the decommissioning of Nuclear Powere Plants (NPPs) and radiochemic...
At the present time the primary problem in a closed nuclear fuel cycle is the management of high lev...
The following presentation is an update to a previous annotation, i.e., WINCO-1138. The literature s...
ABSTRACT Nuclear operations have resulted in the accumulation of large quantities of contaminated me...
The behavior of heavy metals and radionuclides during high-temperature treatment is very important f...
The Research Objectives of this project are to characterize and optimize the use of molten slags to ...
To consolidate metallic waste that is residual from Argonne National Laboratory's electrometallurgic...
Treatment of spent Russian fuel using a Melt-Dilute (MD) process is proposed to consolidate fuel ass...
An electrometallurgical treatment process has been developed by Argonne National Laboratory to conve...
A physico-chemical model of zinc recovery, in the melt ideal mixing regime, has been developed. From...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...