NUCLEAR TECHNIQUES, Volume. 46, Issue 1, 010002(2023)
Nuclide separation technology and engineering application of radioactive oil for NPPs
Figures & Tables(10)
Fig. 2. Experimental device of nuclide separation and purification treatment for radioactive oil
Fig. 3. Engineering device of nuclide separation and purification treatment for radioactive oil(a) Oxidative aging treatment unit, (b) Circulating filtration treatment unit
Fig. 5. Mass (percent) distribution of sludge with different particle sizes
Fig. 6. Diagram of sampling location of 400 L temporary storage barrel for radioactive oil after treatment (a) Top view, (b) Side view
Table 1. 60Co and 137Cs as a percentage of total gamma
View tableView in ArticleTable 1. 60Co and 137Cs as a percentage of total gamma
核素
Nuclide
1号样品
Sample No.1 / %
2号样品
Sample No.2 / %
3号样品
Sample No.3 / %
4号样品
Sample No.4 / %
合计Total 97.49 97.47 97.70 98.10 137Cs 65.83 60.76 53.89 51.29 60Co 31.66 36.71 43.81 46.80
Table 2. Oxidative aging experimental results of radioactive oil
View tableView in ArticleTable 2. Oxidative aging experimental results of radioactive oil
序号
No.
废油量 Volume/ mL 反应温度Temperature/ ℃ 反应时间 Time / d 去污系数
Decontamination factor
137Cs 60Co γT 1 500 160 7 198.84 97.68 116.96 2 12 249.70 157.63 179.02 3 140 12 6.14 10.01 8.41
Table 3. Activity concentration of γ nuclide
View tableView in ArticleTable 3. Activity concentration of γ nuclide
核素Nuclide 限值要求Limits
/ Bq∙g-1
活度浓度 Activity concentration / Bq∙g-1 最大值Maximum 平均值Average 标准差Standard deviation 95Zr 1.0 <2.66×10-3 <1.72×10-3 <6.04×10-4 125Sb 0.1 <5.77×10-3 <3.48×10-3 <1.19×10-3 124Sb 1.0 <1.61×10-3 <1.01×10-3 <2.76×10-4 95Nb 0.1 <1.55×10-3 <1.01×10-3 <2.80×10-4 54Mn 0.1 <1.51×10-3 <1.01×10-3 <2.66×10-4 59Fe 1.0 <3.16×10-3 <2.25×10-3 <5.74×10-4 137Cs 0.1 <1.91×10-3 <1.19×10-3 <3.24×10-4 134Cs 0.1 <1.58×10-3 <9.98×10-4 <2.47×10-4 60Co 0.1 <2.48×10-3 <1.64×10-3 <4.24×10-4 58Co 1.0 <1.45×10-3 <9.80×10-4 <2.74×10-4 110m Ag 0.1 <1.57×10-3 <9.91×10-4 <2.93×10-4 总γ Total γ ― <2.52×10-2 <1.63×10-2 <4.75×10-3
Table 4. Additional dosage caused by heat supply process of oil after treatment incineration
View tableView in ArticleTable 4. Additional dosage caused by heat supply process of oil after treatment incineration
情景Scenario 附加剂量Additional dosage / μSv∙a-1 运输Transportation 正常Normal 司机Driver 运输废油的外照射待积有效剂量
Committed effective dose for external irradiation of oil transportation
8.53×10-2 事故Accident 单次泄露受污染土壤致有效剂量Effective dose caused by single time leakage of contaminated soil 3.68 单次失火烟气吸入致内照射有效剂量Effective dose of internal exposure caused by single time fire smoke inhalation 6.62×10-6 焚烧供热Heat supply process of incineration 工人Worker 焚烧炉运行和焚烧灰收集、储运造成的外照射剂量External exposure dose caused by incinerator operation and incineration ash collection, storage and transportation 2.00×10-4 接收、取样和监测废物内照射剂量Internal exposure dose caused by receiving, sampling and monitoring of waste 3.49×10-8 焚烧炉维修吸入内照射剂量Inhalation internal exposure dose for incinerator maintenance 1.40×10-8 焚烧烟囱排放吸入内照射剂量Inhalation internal exposure dose from incineration chimney 1.93×10-20
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Wendong FENG, Xiaoping HE, Hongxiang AN, Caiyuan DENG, Meilan JIA, Yong WAN, Chao GAO, Zhaofeng LIU, Yufei WANG. Nuclide separation technology and engineering application of radioactive oil for NPPs[J]. NUCLEAR TECHNIQUES, 2023, 46(1): 010002
Paper Information
Category: Research Articles
Received: Oct. 21, 2022
Accepted: --
Published Online: Feb. 17, 2023
The Author Email: FENG Wendong (fwd1986andy@126.com)
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