In-situ Tritium Recovery Experiments of Blanket In-pile Mockup with Li_2TiO_3 Pebble Bed in Japan

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概要

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• Lithium titanate (Li2TiO3) is one of the most attractive tritium breeders for breeding blanket in fusion reactor from view points of low tritium inventory, high chemical stability and so on. The data on the performance of a blanket mockup with pebble bed under neutron irradiation is needed for the design of breeding blanket. To obtain such data, two kinds of the blanket in-pile mockups with Li2TiO3 pebble bed were developed and the in-situ tritium recovery experiments were carried out in the Japan Materials Testing Reactor (JMTR). In these studies, effects of various parameters, i.e., irradiation temperature, sweep gas flow rate, etc., on the tritium recovery behavior from Li2TiO3 pebble bed were evaluated. It was found that the tritium recovery (R) to tritium generation (G) ratio (R⁄G) increased with increasing the temperature of Li2TiO3 pebble bed and was saturated when the temperature of Li2TiO3 pebble bed at the outside edge exceeded 300°C. Additionally, the sweep gas flow rate in the range of 100 to 900 cm3/min affected very little the tritium recovery from Li2TiO3 pebble bed. A good prospect for the design of breeding blankets using Li2TiO3 pebble bed was obtained from these results of in-situ experiments.

• 一般社団法人 日本原子力学会の論文
• 2001-11-25

著者

• Tsuchiya Kunihiko

  Oarai Research Establishment Japan Atomic Energy Research Instiute

• ENOEDA Mikio

  Naka Fusion Research Establishment, Japan Atomic Energy Research Institute

• Enoeda Mikio

  Naka Research Establishment Japan Atomic Energy Research Institute

• NAKAMICHI Masaru

  Oarai Research Establishment, Japan Atomic Energy Research Instiute

• NAGAO Yoshiharu

  Oarai Research Establishment, Japan Atomic Energy Research Instiute

• OSAKI Toshio

  ITER Garching Joint Work Site

• TANAKA Satoru

  University of Tokyo

• KAWAMURA Hiroshi

  Oarai Research Establishment, Japan Atomic Energy Research Instiute

• Nakamichi M

  Oarai Research Establishment Japan Atomic Energy Research Instiute

• Nakamichi Masaru

  Oarai Research Establishment Japan Atomic Energy Research Institute

• Nagao Yoshiharu

  Oarai Research Establishment Japan Atomic Energy Research Instiute

• Kawamura Hiroshi

  Oarai Research Establishment Japan Atomic Energy Research Institute

• Kawamura Hiroshi

  Oarai Research Establishment Japan Atomic Energy Research Instiute

関連論文

• Low Cycle Fatigue Lifetime of HIP Bonded Bi-metallic First Wall Structures of Fusion Reactors
• Nuclear and Thermal Analyses of Supercritical-water-cooled Solid Breeder Blanket for Fusion DEMO Reactor
• In-situ Tritium Recovery Experiments of Blanket In-pile Mockup with Li_2TiO_3 Pebble Bed in Japan
• Characterization of Chemical Densified Coating as Tritium Permeation Barrier

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