Predictive Analysis of the Radiation Exposure for the Primary Cooling System of the Rated Power Operation of MONJU

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  • 「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
  • 「 モ ンジュ 」 テイカク ウンテン デ ノ 1ジ レイキャクケイ ノ ホウシャセン ヒバクセンリョウ ノ ヨソク カイセキ

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Abstract

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.

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