TY - GEN
T1 - Strategic minimization of high level waste from pyroprocessing of spent nuclear fuel
AU - Simpson, Michael F.
AU - Yoo, Tae Sic
AU - Benedict, Robert W.
AU - Phongikaroon, Supathorn
AU - Frank, Steven
AU - Sachdev, Prateek
AU - Hartman, Kellianne
PY - 2007
Y1 - 2007
N2 - The pyroprocessing of spent nuclear fuel results in two high-level waste streams - ceramic and metal waste. Ceramic waste contains active metal fission productloaded salt from the electrorefining, while the metal waste contains cladding hulls and undissolved noble metals. While pyroprocessing was successfully demonstrated for treatment of spent fuel from Experimental Breeder Reactor-II in 1999, it was done so without a specific objective to minimize high-level waste generation. The ceramic waste process uses "throw- away" technology that is not optimized with respect to volume of waste generated. In looking past treatment of EBR-II fuel, it is critical to minimize waste generation for technology developed under the Global Nuclear Energy Partnership (GNEP). While the metal waste cannot be readily reduced, there are viable routes towards minimizing the ceramic waste. Fission products that generate high amounts of heat, such as Cs and Sr, can be separated from other active metal fission products and placed into short-term, shallow disposal. The remaining active metal fission products can be concentrated into the ceramic waste form using an ion exchange process. It has been estimated that ion exchange can reduce ceramic highlevel waste quantities by as much as a factor of 3 relative to throw-away technology.
AB - The pyroprocessing of spent nuclear fuel results in two high-level waste streams - ceramic and metal waste. Ceramic waste contains active metal fission productloaded salt from the electrorefining, while the metal waste contains cladding hulls and undissolved noble metals. While pyroprocessing was successfully demonstrated for treatment of spent fuel from Experimental Breeder Reactor-II in 1999, it was done so without a specific objective to minimize high-level waste generation. The ceramic waste process uses "throw- away" technology that is not optimized with respect to volume of waste generated. In looking past treatment of EBR-II fuel, it is critical to minimize waste generation for technology developed under the Global Nuclear Energy Partnership (GNEP). While the metal waste cannot be readily reduced, there are viable routes towards minimizing the ceramic waste. Fission products that generate high amounts of heat, such as Cs and Sr, can be separated from other active metal fission products and placed into short-term, shallow disposal. The remaining active metal fission products can be concentrated into the ceramic waste form using an ion exchange process. It has been estimated that ion exchange can reduce ceramic highlevel waste quantities by as much as a factor of 3 relative to throw-away technology.
UR - https://www.scopus.com/pages/publications/45149086744
M3 - Conference contribution
AN - SCOPUS:45149086744
SN - 0894480553
SN - 9780894480553
T3 - GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
SP - 1394
EP - 1397
BT - GLOBAL 2007
T2 - GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
Y2 - 9 September 2007 through 13 September 2007
ER -