Journal of Radiation Research and Radiation Processing, Volume. 41, Issue 3, 030601(2023)

Radiation protection for foreign body salvage work in primary of nuclear power plant

Weiping XIE*... Xihuan ZHAO, Hao CHEN, Quanli CHEN and Shenglong LIU |Show fewer author(s)
Author Affiliations
  • Jiangsu Nuclear Power Co. Ltd., Lianyungang 222000, China
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    Figures & Tables(8)
    Physical and chemical transformation process of corrosion products
    Design of special transfer shielding device 1. Head plugs;2. Lug fixing buckle;3. Chain link buckle;4. Filter cartridge;5. Cabinet;6. Base fixing buckle;7. Latch;8. Push-pull handle;9. Pedestal;10. Brake;11. Mobile wheels;12. Flared shape
    schematic diagram of the high discharge waste storage container
    Schematic diagram of additional shielding sleeve
    • Table 1. Radiation risk of foreign body salvage operation in one-loop

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      Table 1. Radiation risk of foreign body salvage operation in one-loop

      作业关键点

      Assignment key points

      辐射风险

      Radiation risk

      解决措施

      Solution measures

      异物出水

      Foreign body out of the water

      异物失去水体的屏蔽作用,附近区域的辐射水平会快速上升

      The foreign body loses the shielding effect of the water body and the

      radiation level in the nearby area will rise rapidly

      设计专用的转运屏蔽装置

      Design of special transit shields

      异物转运

      Foreign body transfer

      转运过程会导致附近区域的辐射水平升高

      The transshipment process can lead to elevated radiation levels in the

      immediate area

      划定转运隔离区域

      Delineate the transfer

      isolation area

      异物贮存

      Foreign body storage

      异物导入至贮存容器后,会造成贮存容器附近的辐射水平升高

      storage container will cause an increase in radiation levels in the vicinity of the storage container

      设计高放废物贮存容器

      Design of high discharge waste storage containers

    • Table 2. Nuclear power plant first circuit salvage foreign body out of water and transfer during the isolation area control requirements

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      Table 2. Nuclear power plant first circuit salvage foreign body out of water and transfer during the isolation area control requirements

      专用转运屏蔽装置接触剂量率

      Posure dose rate

      隔离区域范围和管控要求

      Isolation area scope and control requirements

      H*≤200 Sv/h

      对2 m内的影响范围进行隔离,隔离区域内无关人员进行清场

      Isolation of the impact area within 2 meters, the isolation of the area of irrelevant personnel to clear the field

      200<H*≤600 Sv/h

      对3 m内的影响范围进行隔离,隔离区域内无关人员进行清场

      Isolation of the impact area within 3 meters, the isolation of the area of irrelevant personnel to clear the field

      600<H*

      1 000 Sv/h

      对反应堆大厅进行隔离,隔离区域内无关人员进行清场

      Isolation of the reactor's hall and clearing of extraneous personnel in the isolation area

      H*>1 000 Sv/h

      禁止出水,需要制定专门的处理方案(如先放至乏燃料水池内等)

      Prohibit the discharge of water and require a special treatment plan (e.g., first release into the spent fuel pool, etc.)

    • Table 3. Shielding attenuation multiplier for storage containers and additional shielding sleeves

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      Table 3. Shielding attenuation multiplier for storage containers and additional shielding sleeves

      设备

      Equipment

      屏蔽层厚度

      Shield

      thickness

      / cm

      屏蔽材料

      Shielding materials

      等效混凝土厚度

      Equivalent

      concrete thickness / cm

      减弱倍数

      Weakening multiplier

      贮存容器

      Storage containers

      52

      钢筋混凝土

      Reinforced concrete

      79.71.4×103

      附加屏蔽套

      Additional shielding sleeve

      14

      碳钢

      Carbon Steel

      46.52.696×105

      贮存容器+附加屏蔽套Storage container +

      additional shielding sleeve

      52+14

      钢筋混凝土+碳钢

      Reinforced concrete + carbon steel

      126.22.7×105
    • Table 4. Comparison of theoretical calculations and measured values

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      Table 4. Comparison of theoretical calculations and measured values

      接触剂量率

      / (mSv∙h-1)

      Exposure dose rate

      不使用屏蔽容器1 m处剂量率理论计算值 / (mSv∙h-1)

      Theoretical calculation of dose rate at 1 m without shielding container

      使用转运屏蔽容器剂量率(1 m处)理论计算值 / (μSv∙h-1)

      Theoretical calculation of dose rate (at 1 m) using transit shielding container

      实测值

      / (μSv∙h-1)

      Measured value

      使用高放废物容器贮存剂量率(1 m处)理论计算值 / (μSv∙h-1)

      Theoretical calculation of dose rate (at 1 m) using high discharge waste containers for storage

      实测值

      / (μSv∙h-1)

      Measured value

      1 300131311.69.38.6
      >400443.62.92.5
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    Weiping XIE, Xihuan ZHAO, Hao CHEN, Quanli CHEN, Shenglong LIU. Radiation protection for foreign body salvage work in primary of nuclear power plant[J]. Journal of Radiation Research and Radiation Processing, 2023, 41(3): 030601

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    Paper Information

    Category: Research Articles

    Received: Aug. 1, 2022

    Accepted: Sep. 7, 2022

    Published Online: Jul. 24, 2023

    The Author Email: XIE Weiping (xieweiping2008@163.com)

    DOI:10.11889/j.1000-3436.2022-0076

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