Developed by
Department of Chemistry
Radiochemistry
University of Helsinki
The aim of this exercise is to learn basic practises and safe working methods while working with radionuclides in a radiochemistry laboratory. Furthermore, the students will be introduced to sample preparation for unsealed source measurement and they will learn how to perform a surface contamination measurement.
Protection from external radiation
The storage and application of radionuclides requires the setting up of appropriate shielding from their damaging external radiation. The most noteworthy external radiation types are gamma, high-energy beta and neutron radiations. Alpha and low-energy beta radiations are not capable, for example, of penetrating through the walls of a glass container. The most important methods for protection from external radiation are:
Protection from internal radiation – radionuclide radiation poisoning aka radiotoxicity
Precautions should be taken when working with radionuclides to prevent them from getting into the body. Internal contamination, especially by alpha and low-energy beta nuclides, can be more dangerous than their damaging external radiation. The most toxic internal radiation sources are alpha emitters. The next listing classifies some common radionuclides according to their level of radiotoxicity:
Radiotoxicity classification of some commonly used radionuclides
a) Group 1 (highly radiotoxic): 210Pb, 210Po, 226Ra, 227Ac, 238Pu, 240Pu, 241Am, 252Cf
b) Group 2 (radiotoxic): 60Co, 90Sr, 106Ru, 110mAg, 124I, 125I, 131I, 134Cs, 137Cs, 152Eu, 154Eu
c) Group 3 (moderately radiotoxic): 14C, 22Na, 24Na, 32P, 33P, 45Ca, 54Mn, 55Fe, 59Fe, 57Co, 58Co, 63Ni, 65Zn, 76As, 85Sr, 95Zr, 99Mo, 203Hg
d) Group 4 (slightly radiotoxic): 3H, 11C, 18F, 99mTc, 129I, 201Tl
Laboratory working practises with radionuclides
Before you start working with radionuclides, PLAN your work well. It is important to know with what kind of substance you are working: what is the nuclide’s half-life, radiation type, energy and radiotoxicity. Of the following certain “laboratory rules”, some are to be followed without exception, and others are to be followed when the need arises:
Specific guidelines on the radiation safety requirements of a radionuclide laboratory are in regulatory guides of national radiation and nuclear safety authorities.
Decontamination – washing labware and hands, and monitoring of workers and work areas
Each contamination requires is own appropriate decontamination method. The following are some examples:
a) If you get radioactive solution in contact with your skin, wipe the solution away with absorbent tissue paper and wash the skin thoroughly. Monitor the contaminated area if necessary. Do not use acids, bases, solvents or strong detergents. Brush, but not so vigorously, that the skin would break. Remember also your palms and lower arms.
b) If radioactive solution spills onto the table or floor, wipe it first with dry tissue paper, then with tissue paper dampened with dilute acid or EDTA solution, and finally with tissue paper moistened with water. Monitor the contaminated area if necessary. Wear protective gloves during the clean-up procedure.
c) If solid radioactive material spreads onto the table or floor, collect it with moistened tissue paper. Proceed afterwards with the decontamination steps described in b).
The method for washing labware depends on the radionuclide activity and the quantity of solid material. The following are general washing guidelines:
Handling radioactive waste
The handling and storage of radioactive waste follow several criteria:
The principal rule is that radioactive waste is handled immediately after completion of the work and that waste is stored only when clearly justified (e.g., aging of substances containing short-lived radionuclides). Waste for storage should be labelled well (radionuclide, activity, date activity determined, chemical form, responsible person, when and how the waste is to be disposed). Specific guidelines regarding radioactive waste and its discharge are in regulatory guides of national radiation and nuclear safety authorities.
Solution waste is stored in sufficiently large (> 10 L) plastic containers with wide mouths, and is disposed of sensibly in accordance with optimization principles. Solution waste is divided most commonly according to radionuclide half-life:
Solutions containing organic solvents should be stored separately. Liquid scintillation solutions can be sent for incineration at a waste treatment facility in their measurement bottles packed into a metal barrel. Liquid scintillation waste has its own activity limits, which are worthwhile considering already when planning your work. Liquid scintillation bottles tend to swell and leak, and so they should be sealed in plastic bags before dumping in a metal barrel.
Solid waste should be separated depending on activity for disposal to normal waste, transportation to a dumping site or final disposal. Sharp and other dangerous objects must be protected before being disposed of, and objects of practical value should be broken.
Disposal of contaminated glass and plastic waste depends on the level of contamination and cost. Strongly contaminated glassware is to be disposed of as per radioactive waste if its activity is high and it is difficult to clean. Glassware though tends generally to be cleaned. Plastic ware, such as measurement vials, are considered disposable and immediately after the work is completed are handled as per solid waste. Slightly contaminated plastic ware can be washed and reused in order to minimize waste and costs.
Performed the exercise on a tray, and always keep absorbent cellulose available. Wear gloves when pipetting. Use an adjustable automatic pipette and change tips between different solutions. Never contaminate the pipette by turning it so that the tip is uppermost.
Preparation of 32P samples
Detecting surface decontamination
Fill in the exercise form provided, and submit it within two week after completion of the exercise.
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This project has received funding from the Euratom research and training programme 2019–2020 under grant agreement No. 945301.