Abstract
A study on the voloxidation process has been conducted in order to contribute to the development of tritium control process in the head-end of reprocessing. The oxidation and reduction behavior of a slightly irradiated UO{sub 2} fuel and the tritium release behavior from the fuel were obtained in experiments by using a ball mill type reactor (capacity: 2 kg-UO{sub 2}/batch). The results are summarized as follows: (1) The oxidation reaction of the fuel in cladding was described with `a constant flux model`. (2) The reduction reaction of the pulverized powder was described with `a core diminishing model`. (3) About 60 % of the tritium was released with the oxidation of the fuel and additional treatment of sweeping with nitrogen gas for 2 hrs was needed to release more than 99.9 % of the tritium. It was found that the reduction step for tritium release was not required after the oxidation. (4) Several technical data were obtained on the stability of rotary seal of voloxidizer and on the confinement of powder fuel by a nickel fiber filter. The results of preliminary system analysis using the experimental data show that the voloxidation process without reduction step is effective to confine tritium into
More>>
Uchiyama, Gunzo;
Yamazaki, Kazunobu;
Sugikawa, Susumu;
Maeda, Mitsuru;
Tsujino, Takeshi;
[1]
Kitamura, Masafumi
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Uchiyama, Gunzo, Yamazaki, Kazunobu, Sugikawa, Susumu, Maeda, Mitsuru, Tsujino, Takeshi, and Kitamura, Masafumi.
Development of voloxidation process for tritium control in reprocessing.
Japan: N. p.,
1991.
Web.
Uchiyama, Gunzo, Yamazaki, Kazunobu, Sugikawa, Susumu, Maeda, Mitsuru, Tsujino, Takeshi, & Kitamura, Masafumi.
Development of voloxidation process for tritium control in reprocessing.
Japan.
Uchiyama, Gunzo, Yamazaki, Kazunobu, Sugikawa, Susumu, Maeda, Mitsuru, Tsujino, Takeshi, and Kitamura, Masafumi.
1991.
"Development of voloxidation process for tritium control in reprocessing."
Japan.
@misc{etde_10132214,
title = {Development of voloxidation process for tritium control in reprocessing}
author = {Uchiyama, Gunzo, Yamazaki, Kazunobu, Sugikawa, Susumu, Maeda, Mitsuru, Tsujino, Takeshi, and Kitamura, Masafumi}
abstractNote = {A study on the voloxidation process has been conducted in order to contribute to the development of tritium control process in the head-end of reprocessing. The oxidation and reduction behavior of a slightly irradiated UO{sub 2} fuel and the tritium release behavior from the fuel were obtained in experiments by using a ball mill type reactor (capacity: 2 kg-UO{sub 2}/batch). The results are summarized as follows: (1) The oxidation reaction of the fuel in cladding was described with `a constant flux model`. (2) The reduction reaction of the pulverized powder was described with `a core diminishing model`. (3) About 60 % of the tritium was released with the oxidation of the fuel and additional treatment of sweeping with nitrogen gas for 2 hrs was needed to release more than 99.9 % of the tritium. It was found that the reduction step for tritium release was not required after the oxidation. (4) Several technical data were obtained on the stability of rotary seal of voloxidizer and on the confinement of powder fuel by a nickel fiber filter. The results of preliminary system analysis using the experimental data show that the voloxidation process without reduction step is effective to confine tritium into a small part of reprocessing plants. (author).}
place = {Japan}
year = {1991}
month = {Nov}
}
title = {Development of voloxidation process for tritium control in reprocessing}
author = {Uchiyama, Gunzo, Yamazaki, Kazunobu, Sugikawa, Susumu, Maeda, Mitsuru, Tsujino, Takeshi, and Kitamura, Masafumi}
abstractNote = {A study on the voloxidation process has been conducted in order to contribute to the development of tritium control process in the head-end of reprocessing. The oxidation and reduction behavior of a slightly irradiated UO{sub 2} fuel and the tritium release behavior from the fuel were obtained in experiments by using a ball mill type reactor (capacity: 2 kg-UO{sub 2}/batch). The results are summarized as follows: (1) The oxidation reaction of the fuel in cladding was described with `a constant flux model`. (2) The reduction reaction of the pulverized powder was described with `a core diminishing model`. (3) About 60 % of the tritium was released with the oxidation of the fuel and additional treatment of sweeping with nitrogen gas for 2 hrs was needed to release more than 99.9 % of the tritium. It was found that the reduction step for tritium release was not required after the oxidation. (4) Several technical data were obtained on the stability of rotary seal of voloxidizer and on the confinement of powder fuel by a nickel fiber filter. The results of preliminary system analysis using the experimental data show that the voloxidation process without reduction step is effective to confine tritium into a small part of reprocessing plants. (author).}
place = {Japan}
year = {1991}
month = {Nov}
}