• Journal of Radiation Research and Radiation Processing
  • Vol. 41, Issue 3, 030601 (2023)
Weiping XIE*, Xihuan ZHAO, Hao CHEN, Quanli CHEN, and Shenglong LIU
Author Affiliations
  • Jiangsu Nuclear Power Co. Ltd., Lianyungang 222000, China
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    DOI: 10.11889/j.1000-3436.2022-0076 Cite this Article
    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 Copy Citation Text show less
    Physical and chemical transformation process of corrosion products
    Fig. 1. 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
    Fig. 2. 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
    Fig. 3. schematic diagram of the high discharge waste storage container
    Schematic diagram of additional shielding sleeve
    Fig. 4. Schematic diagram of additional shielding sleeve

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

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

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

    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
    Table 4. Comparison of theoretical calculations and measured values
    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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