Occupational radiation exposure during removal of radioactive reactor components from GRR-1 pool.
The aim of the study was to control occupational exposure during the removal of radioactive reactor components from a Greek research reactor pool. The method comprised the prediction of the radiation levels, the design of special shielding structures and the occupational dose assessment. Activation calculations were performed using the FISPACT code to predict the source term. Monte Carlo simulations using MCNP code were utilized to estimate the ambient dose equivalent rates. The results of the calculations were verified by measurements and were found to be in good agreement. Thermoluminescence dosemeter (TLD) and electronic personal dosemeter (EPD) were implemented to measure the radiation exposure of the workers. The total collective dose of 14 participating workers was 0.15 man mSv. The maximum individual effective dose was 0.02 mSv, and the maximum extremity equivalent dose was 0.09 mSv. The discussed method provides a useful tool enabling work planning during reactor decommissioning and renovation activities ensuring that exposures will be maintained ALARA.
Institute on Nuclear Technology, Radiation Protection, NCSR Demokritos, Aghia Paraskevi 15310, Greece. dimitris@ipta.demokritos.gr
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Tzika
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Stamatelatos
D003198:Computer Simulation; D004867:Equipment Design; D006801:Humans; D008422:Materials Testing; D009010:Monte Carlo Method; D009502:Neutrons; D009688:Nuclear Reactors; D016273:Occupational Exposure / Q000517:prevention & control*; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000295:instrumentation* / Q000379:methods*; D011835:Radiation Protection / Q000379:methods*; D011868:Radioisotopes / Q000032:analysis; D011874:Radiometry / Q000295:instrumentation* / Q000379:methods; D013819:Thermoluminescent Dosimetry / Q000295:instrumentation* / Q000379:methods
D011868:Radioisotopes