Reduction in Degree of Absorber-Cladding Mechanical Interaction by Shroud Tube in Control Rods for the Fast Reactor
スポンサーリンク
概要
- 論文の詳細を見る
Research and development of a long-life control rod for fast reactors is being conducted at Joyo. One of the challenges in developing a long-life control rod is the restraint of absorber-cladding mechanical interaction (ACMI). First, a helium-bonding rod was selected as a control rod for the experimental fast reactor Joyo, which is the first liquid metal fast reactor in Japan. Its lifetime was limited by ACMI, which is induced by the swelling and relocation of B4C pellets. To restrain ACMI, a shroud tube was inserted into the gap between the B4C pellets and the cladding tube. However, once B4C pellets cracked and broke into small fragments, relocation occurred. After this, the narrow gap closed immediately as the degree of B4C pellet swelling increased. To solve this problem, the gap was widened during design, and sodium was selected as the bonding material instead of helium to restrain the increase in pellet temperature. Irradiation testing of the modified sodium-bonding control rod confirmed that ACMI would be restrained by the shroud tube regardless of the occurrence of B4C pellet relocation. As a result of these improvements, the estimated lifetime of the control rod at Joyo was doubled. In this paper, the results of postirradiation examination are reported.
- 2011-04-01
著者
-
DONOMAE Takako
Japan Atomic Energy Agency
-
KATSUYAMA Kozo
Japan Atomic Energy Agency
-
SOGA Tomonori
Japan Atomic Energy Agency, Oarai R&D Center
-
TACHI Yoshiaki
Japan Atomic Energy Agency
-
MAEDA Koji
Japan Atomic Energy Agency
-
Yamamoto Masaya
Japan Atomic Energy Agency
-
Soga Tomonori
Japan Atomic Energy Agency
関連論文
- Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups
- Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups
- Reduction in Degree of Absorber-Cladding Mechanical Interaction by Shroud Tube in Control Rods for the Fast Reactor
- Core Modification to Improve Irradiation Efficiency of the Experimental Fast Reactor Joyo
- Retention and Release of Tritium in B_4C Irradiated as Control Rod of Fast Breeder Reactor
- Reduction in Degree of Absorber-Cladding Mechanical Interaction by Shroud Tube in Control Rods for the Fast Reactor
- Core Modification to Improve Irradiation Efficiency of the Experimental Fast Reactor Joyo
- Irradiation Test of Fuel Containing Minor Actinides in the Experimental Fast Reactor Joyo