`11´B4C の中性子照射効果とその回復挙動

  • 堂野前 貴子
    独立行政法人日本原子力研究開発機構大洗研究開発センター燃料材料試験部
  • 舘 義昭
    独立行政法人日本原子力研究開発機構大洗研究開発センター燃料材料試験部
  • 関根 学
    原子力技術株式会社大洗事業所
  • 諸橋 裕子
    独立行政法人日本原子力研究開発機構敦賀本部高速増殖炉研究開発センターもんじゅ開発部
  • 赤坂 尚昭
    独立行政法人日本原子力研究開発機構大洗研究開発センター燃料材料試験部
  • 小野瀬 庄二
    独立行政法人日本原子力研究開発機構大洗研究開発センター燃料材料試験部

書誌事項

タイトル別名
  • Neutron Irradiation Effects on 11B4C and Recovery by Annealing
  • 11B4Cの中性子照射効果とその回復挙動
  • 11B4C ノ チュウセイシ ショウシャ コウカ ト ソノ カイフク キョドウ

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抄録

Use of moderator materials in a fast breeder reactor is effective for transmutation technology, and 11B4C is one of the candidates. Up to now, the behavior of 10B4C as the control rod material is well known, but that of 11B4C has hardly been investigated. In this paper, irradiation effects of 11B4C pellet irradiated in the experimental fast reactor JOYO were studied. From the experimental results, it was observed that no macro-cracks were recognized but bubble nucleation was found in the grain and along the grain boundaries of 11B4C. Furthermore, it was shown that the thermal conductivity of 11B4C was higher than that of 10B4C. During the annealing from room temperature to 1400°C, two recovery stages were found on thermal conductivity. It was suggested that the recovery of B4C was related to the volume and distribution of helium bubbles. Since the 11B4C pellet was mechanically more stable compared with the 10B4C pellet under irradiation, it was shown that 11B4C had high applicability for a moderator material.<br>

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