Introduction

Radioactivity is the ability of elements, such as uranium, to release radiation as their atomic nuclei instability state. The metastable element emits radiation in the form of alpha-particles, beta-particles, gamma-rays or neutron particles. The radon (Rn), one of the radioactive materials, has been detected more than EPA standard level at 100 Bq m−3 [1] in products used in daily life or new apartments. Radon is a radiation nuclide that emits alpha-particles and was tested with strontium-90 (Sr-90), in order to verify the efficiency of the coefficient of liquid scintillation using the scintillation phenomenon during analysis of these nuclides.

Sr-90 has a half-life of 28.8 years, emitting 0.546 MeV of beta-particles and decaying to yttrium-90 (Y-90, halflife of 2.7 days). The Sr-90 is generated in large quantities by the fission of uranium-235, and its half-life is moderately long, making it useful in many applications. This chemical property of Y-90 is similar to calcium, so it is absorbed into the body, which has a significant adverse effect on human being such as bone marrow, leukemia, and genetic mutations [2].

As can see in Fig. 1, liquid scintillator counter (LSC) produces instantaneous light in proportion to the energy lost in the fluorescent material when radiation is introduced into a substance consisting of several types of fluorescent material, which can be detected by amplifying the weak radiation emitted by Sr-90. However, existing LSC measures specimens by dissolving them into scintillators. Therefore, the effect of impurities on samples or solvents causes a quenching phenomenon in which the luminous efficiency of the scintillator decreases [3].

Fig. 1
figure 1

Principle of liquid scintillation counting measurement

Experimental

As shown in Fig. 2, 1 mL of 90Sr/90Y standard solution provided by Korea Research Institute of Standards and Science (KRISS 09SR90V26, 1053.14 DPM) was passed through a column filled with 2.0 g of Sr-specific resin (Eichrom, Lisle, IL, USA; particle size: 100 to 150 μm) which was placed in 30 mL of 8 M HNO3 (Merck, Darmstadt, Germany) in advance. After then, about 20 mL of 8 M HNO3 solution was added to the column to make Sr-90 adsorb to the resin and Y-90 release [4], and deionized water was used to strip the adsorbed Sr-90 from the resin until the volume of receiving solution was up to 30 mL. The 30 mL of Sr-90 extract was marked to 50 mL with 0.1 M of HNO3.

Fig. 2
figure 2

The method to separate Sr-90 using Sr specific resin

Results and discussion

Unlike the typical cocktail method, the method for measuring beta-particles is to separate the Sr-90 containing sample and the scintillation cocktail (Ultima Gold and Ultima Gold-LLT, PerkinElmer, Waltham, MA) from each other, as shown in Fig. 3. The sample was placed in a 5 mL polyethylene vial, and then the vial was placed in a 20 mL low-potassium borosilicate vial containing the liquid scintillator. Finally, the 20 mL vial was shaken and counted by LSC (1220 Quantulus, Wallac, Perkin Elmer, Waltham, MA). The lower limit of detection (LLD) of Sr-90 was calculated to be 0.1 Bq kg-1 according to the reference method [5].

Fig. 3
figure 3

A proposed approach to separate Sr-90 containing samples and scintillation cocktails for beta-particle measurements

Several samples using the Sr-90 extract marked with 0.1 M of HNO3 were prepared to investigate the efficiency of the new method and are listed in Table 1. The amount of nitromethane (quenching agent) and 0.1 M HNO3 in the Sr-90 extract was varied in the J-LLT-R2 ~ R0 and J-UG-R2 ~ R0 samples, respectively. Meanwhile, the amount of nitromethane in the scintillation cocktail instead of the extract was varied too in J-LLT-R2a ~ R0a and J-UG-R2a ~ R0a samples, respectively. For comparison, the normal cocktail method was adopted as J-LLT-RS2 ~ RS0 and J-UG-RS2 ~ RS0, respectively. J-LLT-S2 ~ 0 and J-UG-S2 ~ 0 samples were prepared for another comparison with J-LLT-R2 ~ 0 and J-UG-R2 ~ 0 by utilizing the 90Sr/90Y standard solution provided by KRISS without separation of Y-90 using Sr-specific resin.

Table 1 Sample preparation for a new proposal of cocktail LSC method

Since the amount of Sr-90 in the sample is the same, the value of DPM was 1053.14 as the following [6];

$${\text{DPM}} = \left( {21062.83\;{\text{counts}}/50\;{\text{mL}}\;{\text{sample}}} \right) \times 2.5\;{\text{mL}}\;{\text{sample}}$$

Each prepared sample was measured by LSC for 20 min as shown in Figs. 4 and 5, and the control test with the scintillation cocktail alone showed no specific peaks without Sr-90. However, in the presence of Sr-90 alone, a peak appeared in the channel range of 140–360, and the peak shapes and peak positions were the same as those obtained from the J-LLT-S, J-UG-S, J-LLT-R, J-UG-R, J-LLT-Ra, and J-UG-Ra series of spectra in Fig. 5. On the other hand, an additional peak in the channel ranges from 700 to 850 was detected in the series of J-LLT-S, J-UG-S, J-LLT-R, and J-UG-R, and shifted to 400 by increasing the volume of nitromethane in the series of J-LLT-Ra and J-UG-Ra. Nevertheless, existing conventional cocktail method has much broader peaks across the channel range from 200 to 850 in the series J-LLT-RS and J-UG-RS, as shown in Fig. 4. The long half-life (28.8 years) and high decay constant (6.60 × 10−5 d−1) of Sr-90 (the parent radionuclide), compared to the significantly shorter half-life (2.7 days) and lower decay constant (2.57 × 10−1 d−1) of Y-90 (the daughter radionuclide), put Sr-90 and Y-90 in secular equilibrium, which is the steady state. Therefore, the 14-day changes in radiative equilibrium with Y-90 after Sr-90 extraction using Sr-specific resin were confirmed, and the quenching by nitromethane (quenching agent) was confirmed. In the experimental method using the sample and scintillation cocktail separately, the peaks are sharper and better defined, but the efficiency is very low, about 10%. The distance between the two vials and the thickness of the vials may be the reasons for the low efficiency. The existing conventional cocktail method has a higher efficiency than the other series of the J-LLT-S, J-UG-S, J-LLT-R, J-UG-R, J-LLT-Ra, and J-UG-Ra. The energy of beta-particles is high, so the transmittance is not so good.

Fig. 4
figure 4

LSC results of Sr-90 over time using Sr-90 extracts separated from Sr-90/Y-90 with Sr-specific resins by the existing conventional cocktail methods (series of J-LLT-RS and J-UG-RS)

Fig. 5
figure 5

LSC results of Sr-90 by the separation methods of Sr-90 sample and scintillator (series of J-LLT-S, J-UG-S, J-LLT-R, J-UG-R, J-LLT-Ra, and J-UG-Ra)

Conclusions

After separating the Sr-90 using resin, the radioactivity was measured using liquid scintillator counter. The separation method resulted in sharper peaks in the spectra than the conventional cocktail method, but it can be confirmed that the efficiency is inferior. When drawing the quenching curve, the linearity was poor, and it was a little difficult to grasp the measurement efficiency. However, when measured by the separation method, the peak did not appear sporadically but showed a certain trend. For the separation method, the peak in the channel range of 140 to 360 had the same peak shape and peak position as that obtained from a spectrum in the presence of Sr-90 alone. However, in the series of J-LLT-S, J-UG-S, J-LLT-R, and J-UG-R, additional peak was detected in the channel range of 700 to 850, and in the series of J-LLT-Ra and J-UG-Ra, this peak was shifted to 400 by increasing the amount of nitromethane. The intensity of the peak is not high, but if the peak is consistent, it can be used as an indicator of measurement. In addition, it is possible to measure the sample by preserving it intactly rather than using it as a one-time use. In situations where measurement is hindered by uneven mixing of the sample and scintillator, it is believed that a separate measurement method may be useful for several researchers to overcome the solubility issue in LSC method.