Low levels of Fukushima Dai-ichi NPP-derived radiocesium in marine products from coastal areas in the Sea of Japan (2012-2017).

Radiocesium concentrations in marine biota in coastal areas of the Sea of Japan were < ~0.005-0.02 Bq/kg-wet and ~0.01-0.18 Bq/kg-wet for 134Cs and 137Cs, respectively (2012-2017). The biota-seawater concentration factors were ~25-100, which approximately agreed with those of 137Cs recorded before FDNPP accident. The low levels of 134Cs in marine biota were likely taken up from ambient seawaters. The total of radiocesium concentrations is now equivalent to that in the 1990s based on the ambient water data.

Simple 40K removal by acidified water leaching for estimating low levels of radiocesium in fishery products following Fukushima Dai-ichi Nuclear Power Plant accident.

We developed a simple method for 40K removal by acidified water leaching combined with ammonium phosphomolybdate coprecipitation, for estimating low levels of radiocesium in Japanese flounder. 40K removal from ashed samples was approximately 98%, with the radiocesium yield of ~98%. The treatment reduced the γ-spectral baseline to ~1/5 at ground and ~3/100 at underground levels (1.04 and 0.11 cph/keV, respectively). Faint signal of 134Cs, which is embedded in the Compton continuum of 40K in an untreated sample, was detected.

[Survey of Radioactive Cesium and Potassium Intake from Food Using Duplicate Diet (Fiscal Years 2011-2014)].

Dietary intake of radioactive substances ((134)Cs, (137)Cs, (40)K) from food in fiscal 2011--2014 was surveyed using the duplicate diet method. 1,612 diet samples were collected from general households of 18 prefectures. (134)Cs and (137)Cs were detected in samples from Fukushima Prefecture, Miyagi Prefecture and Tokyo Prefecture. (134)Cs and (137)Cs were detected in 11 samples in fiscal 2011, 12 samples in fiscal 2012, and 7 samples in fiscal 2013, but none was detected in fiscal 2014. The largest radioactivity in a sample was 12 Bq/kg in Fukushima Prefecture in fiscal 2011. The detected levels gradually decreased and were less than 1.0 Bq/kg in fiscal 2014. The maximum estimated dose of radioactive cecium was 0.14 mSv/year in fiscal 2011. Radioactive potassium was detected in every meal, and showed little change through the four years (median around 30 Bq/kg).

[About the contents of 40K, 226Ra and 232Th in forest soils of the Republic of Belarus].

The specific activity of 40K, 232Th and 226Ra in forest soil ecotopes (A2-B2-C2-D2) has been investigated. When the fertility of the soil increases from A2 to D2, then the specific activity of 40K increases in the rooting zone of the soil from 275 ± 6.9 up to 499 ± 11 Bq/kg, 232Th--from 11.8 ± 0.5 to 17.1 ± 1.1 Bq/kg, 226Ra- from 19.2 γ 0.8 to 27.9 ± 1.5 Bq/kg. The calculated capacity of the absorbed dose of γ-radiation conditioned by 40K, 232Th and 226Ra increases from A2 to D2 from 27.5 ± 0.5 to 44.1 ± 1.1 nGy / h at the height of 1 m.

Accurate determination of 4¹Ca concentrations in spent resins from the nuclear industry by accelerator mass spectrometry.

The radiological characterisation of nuclear waste is essential for managing storage sites. Determining the concentration of Long-Lived RadioNuclides (LLRN) is fundamental for their long-term management. This paper focuses on the measurement of low (41)Ca concentrations in ions exchange resins used for primary fluid purification in Pressurised Water Reactors (PWR). (41)Ca concentrations were successfully measured by Accelerator Mass Spectrometry (AMS) after the acid digestion of resin samples, followed by radioactive decontamination and isobaric suppression through successive hydroxide, carbonate, nitrate and final CaF2 precipitations. Measured (41)Ca concentrations ranged from 0.02 to 0.03 ng/g, i.e. from 0.06 to 0.09 Bq/g. The (41)Ca/(60)Co activity ratios obtained were remarkably reproducible and in good agreement with the current ratio used for resins management.

Separation techniques for quantification of radionuclides in environmental samples.

The reliable and quantitative measurement of radionuclides is important in order to determine environmental quality and radiation safety, and to monitor regulatory compliance. We examined soil samples from Podunajske Biskupice, near the city of Bratislava in the Slovak Republic, for the presence of several natural ((238)U, (232)Th, (40)K) and anthropogenic ((137)Cs, (90)Sr, (239)Pu, (240)Pu, (241)Am) radionuclides. The area is adjacent to a refinery and hazardous waste processing center, as well as the municipal incinerator plant, and so might possess an unusually high level of ecotoxic metals. We found that the levels of both naturally occurring and anthropogenic radionuclides fell within the expected ranges, indicating that these facilities pose no radiological threat to the local environment. During the course of our analysis, we modified existing techniques in order to allow us to handle the unusually large and complex samples that were needed to determine the levels of (239)Pu, (240)Pu, and (241)Am activity. We also rated three commercial techniques for the separation of 90Sr from aqueous solutions and found that two of them, AnaLig Sr-01 and Empore Extraction Disks, were suitable for the quantitative and reliable separation of (90)Sr, while the third, Sr-Spec Resin, was less so. The main criterion in evaluating these methods was the chemical recovery of (90)Sr, which was less than we had expected. We also considered speed of separation and additional steps needed to prepare the sample for separation.

Automated production of potassium-38 for the study of myocardial perfusion using positron emission tomography.

The 35Cl(alpha, n)38K nuclear reaction was developed for the routine cyclotron production of repeated multimillicurie batches of 38K for dynamic studies of regional tissue perfusion with positron emission tomography. The objective is to make this isotope available as an alternative to the use of [13N]NH3 and 82Rb for the investigation of flow in experimental and clinical use. A sodium chloride powder target mounted on a water-cooled nickel backing is bombarded with 26 MeV helium-4 ions at a maximum beam current of 25 microA. The target is remotely disconnected from the bombardment port, transported to a hot cell and entirely processed by a computer-controlled system within a total time of less than 4 min. The final pyrogen-free isotonic and sterile solution of 38K has a radionuclidic purity of more than 99.99%. A typical yield of 19 +/- 2 mCi of 38K is obtained at the end of a 30 min bombardment at 10 microA. The production rate at saturation can therefore be estimated to 2.05 +/- 0.2 mCi/microA.