by The Office, for sale by the National Technical Information Service] in [Oakland, Calif.], [Springfield, Va .
Written in English
|Statement||report written by H. H. Yip, L. J. Olguin ; prepared under contract EY-76-C-03-0167, project agreement no. 53 for the San Francisco Operations Office, Department of Energy|
|Series||GA-A ; 15092|
|Contributions||Olguin, L. J., joint author, General Atomic Company, United States. Dept. of Energy. San Francisco Operations Office|
|The Physical Object|
The separation of /sup /U and /sup /U in the reprocessing of HTGR fuels is a key feature of the feed-breed fuel cycle concept. This is attained in the Fort St. Vrain (FSV) reactor by coating the fissile (Th-/sup /U) particles and the fertile (Th-/sup /U) particles separately with silicon carbide (SiC) layers to contain the fission products and to protect the kernels from burning in. In India, reprocessing of aluminum-clad thorium fuel has been carried out on fuel irradiated in the CIRUS reactor. The reprocessing of these rods, which had been irradiated to a level up to kg of U per ton of thorium, and cooled for more than two years, was made in a pilot-scale test facility at BARC and at the IGCAR (Anantharaman et Cited by: 1. Download Citation | Application of Supercritical Fluid Extraction in Reprocessing of Spent Nuclear Fuel | PUREX process is used in the reprocessing of spent nuclear fuel (SNF) for many years. But. Procedia Chemistry 7 () â€“ The Authors. Published by Elsevier B.V. Selection and /or peer-review under responsibility of the Chairman of the ATALANTA Program Committee doi: / ATALANTE International Conference on Nuclear Chemistry for Sustainable Fuel Cycles Possible options for uranium-carbide SNF processing D.V. Cited by: 5.
reprocessing and refabrication of fuel. The protactinium formed in thorium fuel cycle also cause some problems, which need to be suitably resolved. The information on thorium and thorium fuel cycles has been well covered in the IAEA-TECDOC (May ) File Size: 1MB. The principal gaseous wastes in reprocessing of fuel elements from high-temperature gas-cooled reactors (HTR's) arise from the burning head-end step, from the fuel dissolution operation, from the. In the HTGR fuel particles (UC 2 or ThO,), 10 Ci of '~C/ GW(e)-ir will be formed from 25 ppm of nitrogen. whereas "0 in the ThO, will contribute an additional 2 Cli GW(e)-yr. All I~C contained in the fuels may be released in a gas mixture (CO,. CO. CH~, etc.) during fuel . Nuclear fuel is material used in nuclear power stations to produce heat to power is created when nuclear fuel undergoes nuclear fission.. Most nuclear fuels contain heavy fissile actinide elements that are capable of undergoing and sustaining nuclear three most relevant fissile isotopes are uranium, uranium and plutonium
This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. Recently Viewed. Biochemistry. Cyclization of a Cytolytic Amphipathic α-Helical Peptide and Its Diastereomer: Effect on Structure, Interaction with Model Membranes, and Biological Function. EPA/J TRANSPORTATION ACCIDENT RISKS IN THE NUCLEAR POWER INDUSTRY OFFICE OF RADIATION PROGRAMS US. chemical reprocessing plants, fuel fabrication facilities and waste repositories. Flow in Typical LWR Fuel Cycle With 26 Plutonium Recycle 9 Material Flow in Typical HTGR Fuel Cycle 27 10 Material Flow in Typical LMFBR. The safe, secure, reliable and economic management of spent fuel arising from nuclear power reactors is key for the sustainable utilization of nuclear energy and covers many technological aspects related to the storage, transportation, recycling and disposal of the spent fuel and the high level waste (HLW) generated from spent fuel reprocessing. The sustainability of nuclear energy involves.