「もんじゅ」定格運転での1次冷却系の放射線被ばく線量の予測解析 Predictive Analysis of the Radiation Exposure for the Primary Cooling System of the Rated Power Operation of MONJU

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著者

    • 長谷川 正憲 HASEGAWA Masanori
    • (独)日本原子力研究開発機構高速増殖炉研究開発センター Fast Breeder Reactor Research and Development Center, Japan Atomic Energy Agency
    • 前川 嘉治 [他] MAEGAWA Yoshiharu
    • (独)日本原子力研究開発機構高速増殖炉研究開発センター Fast Breeder Reactor Research and Development Center, Japan Atomic Energy Agency
    • 宮原 信哉 MIYAHARA Shinya
    • (独)日本原子力研究開発機構FBRプラント工学研究センター FBR Plant Engineering Center, Japan Atomic Energy Agency

抄録

Radioactive corrosion products (CP) are main source of personal radiation exposure during maintenance without fuel-failure accident in the Liquid-Metal Fast Breeder Reactor (LMFBR) plants. In order to establish the techniques of radiation dose estimation for personnel, program system "DORE" has been developed. The DORE system is constructed by PSYCHE code and QAD code system. The density of each deposited CP of primary coolant system in MONJU was estimated by using the PSYCHE. Moreover, the QAD-CGGP2R code is applied to dose rate calculations for the primary coolant system in MONJU. The dose rate around primary piping system was visualized using AVS software. The predicted values were estimated to be saturated at 2–3 mSv/h in twenty years after the start of operation, and the dose rate reaches 4 mSv/h in domains near the IHX and the cold-leg piping. It has been assumed that the main radiation source is 54Mn in the IHX, primary pump and cold-leg piping region. On the other hand, it was indicated that the contribution to dose rate of the 60Co accounted for approximately 23% in the hot-leg piping region.

Radioactive corrosion products (CP) are main source of personal radiation exposure during maintenance without fuel-failure accident in the Liquid-Metal Fast Breeder Reactor (LMFBR) plants. In order to establish the techniques of radiation dose estimation for personnel, program system "DORE" has been developed. The DORE system is constructed by PSYCHE code and QAD code system. The density of each deposited CP of primary coolant system in MONJU was estimated by using the PSYCHE. Moreover, the QAD-CGGP2R code is applied to dose rate calculations for the primary coolant system in MONJU. The dose rate around primary piping system was visualized using AVS software. The predicted values were estimated to be saturated at 2-3 mSv/h in twenty years after the start of operation, and the dose rate reaches 4 mSv/h in domains near the IHX and the cold-leg piping. It has been assumed that the main radiation source is <sup>54</sup>Mn in the IHX, primary pump and cold-leg piping region. On the other hand, it was indicated that the contribution to dose rate of the <sup>60</sup>Co accounted for approximately 23% in the hot-leg piping region.

収録刊行物

  • 保健物理 : hoken buturi

    保健物理 : hoken buturi 46(4), 304-313, 2011-12-01

    日本保健物理学会

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各種コード

  • NII論文ID(NAID)
    10030135830
  • NII書誌ID(NCID)
    AN00228458
  • 本文言語コード
    JPN
  • 資料種別
    ART
  • ISSN
    03676110
  • NDL 記事登録ID
    023538808
  • NDL 請求記号
    Z16-696
  • データ提供元
    CJP書誌  NDL  IR  J-STAGE 
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