Fabrication of Uranium-Plutonium Mixed Nitride Fuel Pins for Irradiation Tests in JMTR.
スポンサーリンク
概要
- 論文の詳細を見る
Four He-bonded fuel pins containing uranium-plutonium mixed nitride pellets were fabricated for the irradiation tests in JMTR, aiming at understanding the irradiation behavior and demonstrating the feasibility of mixed nitride as an advanced fuel for FBRs. Mixed nitride pellets were prepared by carbothermic reduction of the oxides. One of the fuel pins was fitted with a set of W-Re thermocouples in order to trace the temperature change of pellet center during irradiation. Moreover, ferritic stainless steel was adopted as a cladding material in one fuel pin besides type 316 austenitic stainless steel. In this report, the design and characteristics of mixed nitride fuel pins are described.
- 一般社団法人 日本原子力学会の論文
著者
-
IWAI Takashi
Japan Atomic Energy Agency
-
ARAI Yasuo
Japan Atomic Energy Agency
-
Shiozawa Ken-ichi
Japan Atomic Energy Research Institute
-
SUZUKI Yasufumi
Japan Atomic Energy Research Institute
-
OHMICHI Toshihiko
Japan Atomic Energy Research Institute
-
SASAYAMA Tatsuo
Japan Atomic Energy Research Institute
-
MAEDA Atsushi
Japan Atomic Energy Research Institute
-
IWAI Takashi
Japan Atomic Energy Research Institute
関連論文
- Electrolysis of Burnup-Simulated Uranium Nitride Fuels in LiCl-KCl Eutectic Melts
- Out-of-pile Tests of Simulated Rock-like Oxide(ROX)Fuels
- ICONE11-36475 Research and Development on Accelerator-driven Transmutation System at JAERI
- Effects of Hydrogen/Water Vapor Atmospheres upon Vaporization of UO2-Based Complex Oxides with Sr, Ba, and Cs by Means of High Temperature Mass Spectrometry (高温質量分析特集号)
- Fission Fragment Damage in Epitaxial Film of Uranium Dioxide
- Thermal Diffusivity of Uranium by Laser Pulse Method from 20°to 850℃
- Temperature dependence of time resolved photoluminescence at 512 μm and at 528 μm and magnetic properties of uranium glass (特集 ナノテクノロジーが進めるフェライトおよび磁性微粒子材料の高性能化)
- Magnetic Susceptibility of Uranium Carbonitride
- Phase Equilibria in System U-Pu-W-C
- Gamma-ray production cross sections for aluminum and copper at 5.3-MeV neutron energy.
- Preparation of Neptunium Mononitride by Carbothermic Reduction.
- Fabrication of Uranium-Plutonium Mixed Nitride Fuel Pins for Irradiation Tests in JMTR.
- Measurement of occluded gases released from uranium-plutonium mixed carbide and uranium carbide fuels.
- Carbothermic synthesis of uranium-plutonium mixed carbide.
- Kinetics on carbothermic reduction of UO2+C powders and compacts to UC2.