Abstract
A reprocessing plant with an annual throughput of 1600 metric tons of fuel generates 50 m{sup 3} of incinerable {alpha}-contaminated waste. The reference treatment currently adopted for these wastes is to embed them in cement grout, with a resulting conditioned waste volume of 260 m{sup 3}. The expense of mandatory geological disposal of such volumes justifies examination of less costly alternative solutions. After several years of laboratory and inactive pilot-scale research and development, the Commissariat a l`Energie Atomique has developed a two-step incineration process that is particularly suitable for {alpha}-contaminated chlorinated plastic waste. A 4 kg-h{sup -1} pilot unit installed at the Marcoule Nuclear Center has now logged over 3500 hours in operation, during which the operating parameters have been optimized and process performance characteristics have been determined. Laboratory research during the same period has also determined the volatility of transuranic nuclides (U, Am and Pu) under simulated incineration conditions. A 100 g-h{sup -1} laboratory prototype has been set up to obtain data for designing the industrial pilot facility.
Citation Formats
Vincent, J J, Longuet, T, Cartier, R, and Chaudon, L.
Incineration process for plutonium-contaminated waste.
France: N. p.,
1992.
Web.
Vincent, J J, Longuet, T, Cartier, R, & Chaudon, L.
Incineration process for plutonium-contaminated waste.
France.
Vincent, J J, Longuet, T, Cartier, R, and Chaudon, L.
1992.
"Incineration process for plutonium-contaminated waste."
France.
@misc{etde_10119192,
title = {Incineration process for plutonium-contaminated waste}
author = {Vincent, J J, Longuet, T, Cartier, R, and Chaudon, L}
abstractNote = {A reprocessing plant with an annual throughput of 1600 metric tons of fuel generates 50 m{sup 3} of incinerable {alpha}-contaminated waste. The reference treatment currently adopted for these wastes is to embed them in cement grout, with a resulting conditioned waste volume of 260 m{sup 3}. The expense of mandatory geological disposal of such volumes justifies examination of less costly alternative solutions. After several years of laboratory and inactive pilot-scale research and development, the Commissariat a l`Energie Atomique has developed a two-step incineration process that is particularly suitable for {alpha}-contaminated chlorinated plastic waste. A 4 kg-h{sup -1} pilot unit installed at the Marcoule Nuclear Center has now logged over 3500 hours in operation, during which the operating parameters have been optimized and process performance characteristics have been determined. Laboratory research during the same period has also determined the volatility of transuranic nuclides (U, Am and Pu) under simulated incineration conditions. A 100 g-h{sup -1} laboratory prototype has been set up to obtain data for designing the industrial pilot facility.}
place = {France}
year = {1992}
month = {Dec}
}
title = {Incineration process for plutonium-contaminated waste}
author = {Vincent, J J, Longuet, T, Cartier, R, and Chaudon, L}
abstractNote = {A reprocessing plant with an annual throughput of 1600 metric tons of fuel generates 50 m{sup 3} of incinerable {alpha}-contaminated waste. The reference treatment currently adopted for these wastes is to embed them in cement grout, with a resulting conditioned waste volume of 260 m{sup 3}. The expense of mandatory geological disposal of such volumes justifies examination of less costly alternative solutions. After several years of laboratory and inactive pilot-scale research and development, the Commissariat a l`Energie Atomique has developed a two-step incineration process that is particularly suitable for {alpha}-contaminated chlorinated plastic waste. A 4 kg-h{sup -1} pilot unit installed at the Marcoule Nuclear Center has now logged over 3500 hours in operation, during which the operating parameters have been optimized and process performance characteristics have been determined. Laboratory research during the same period has also determined the volatility of transuranic nuclides (U, Am and Pu) under simulated incineration conditions. A 100 g-h{sup -1} laboratory prototype has been set up to obtain data for designing the industrial pilot facility.}
place = {France}
year = {1992}
month = {Dec}
}