Fabrication Technology for MOX Fuel Containing AmO_2 by an In-cell Remote Process
スポンサーリンク
概要
- 論文の詳細を見る
An in-cell remote fabrication technique was developed for MOX fuel pellets containing 3 and 5% americium (Am–MOX fuel pellet). The fuel pellet was fabricated by means of conventional powder metallurgy. A series of fuel pellet fabrication apparatuses were systematically installed in the alpha-gamma cell (hot cell) to protect workers from a strong γ-ray exposure from 241Am, and were remotely controlled from a panel in the operation room outside the hot cells as much as possible. From a preliminary UO2 pellet fabrication run, ball milling of powder for 4 h, pressing at 4 t/cm2 and sintering at 1,700°C for 2 h were determined as a good fabrication, but the ball milling time was too short for the UO2 and Am–PuO2 powders of different morphologies to be uniformly mixed. Then, the 5% Am–MOX fuel pellet of density more than 93% T.D. which is proper to the irradiation in FBR was successfully fabricated by extending the ball milling time for more than 10 h. It was, furthermore, found that the complete cleanup of the powder feeder was necessary in the transition of fabrication runs to prevent the formation of uranium and plutonium spots in the pellets.
- 社団法人 日本原子力学会の論文
- 2004-08-25
著者
-
Koyama Shin-ichi
Japan Atomic Energy Agency
-
Namekawa Takashi
Japan Nuclear Cycle Development Institute
-
YOSHIMOCHI Hiroshi
Japan Nuclear Cycle Development Institute
-
NEMOTO Masanao
Japan Nuclear Cycle Development Institute
-
MONDO Kenji
Japan Nuclear Cycle Development Institute
-
Koyama Shin-ichi
Japan Nuclear Cycle Development Institute
関連論文
- Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity — Irradiation Tests of Np and Np-U Samples in the Experimental Fast Reactor JOYO (JAEA) and the Advanced Test Reactor at INL —
- Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity : Irradiation Tests of Np and Np-U Samples in the Experimental Fast Reactor JOYO (JAEA) and the Advanced Test Reactor at INL
- Fabrication Technology for MOX Fuel Containing AmO_2 by an In-cell Remote Process
- Development of a Multi-functional Reprocessing Process based on Ion-exchange Method by using Tertiary Pyridine-type Resin
- Separation and Utilization of Tc and Other Rare Metal Fission Products by an Extended Aqueous Reprocessing
- Analysis of Curium in Mixed Oxide Fuel Irradiated in the Experimental Fast Reactor JOYO for the Evaluation of Its Transmutation Behavior
- Measurement of Burnup in FBR MOX Fuel Irradiated to High Burnup
- Analysis of Irradiated ^Np in the Experimental Fast Reactor JOYO for the Evaluation of its Transmutation Behavior in a Fast Reactor
- Analysis of Curium Isotopes in Mixed Oxide Fuel Irradiated in Fast Reactor
- Analysis of Minor Actinides in Mixed Oxide Fuel Irradiated in Fast Reactor, (I) Determination of Neptunium-237