Assessment of the neutron dose field around a biomedical cyclotron: FLUKA simulation and experimental measurements

In the planning of a new cyclotron facility, an accurate knowledge of the radiation field around the accelerator is fundamental for the design of shielding, the protection of workers, the general public and the environment.Monte Carlo simulations can be very useful in this process, and their use is constantly increasing. However, few data have been published so far as regards the proper validation of Monte Carlo simulation against experimental measurements, particularly in the energy range of biomedical cyclotrons.In this work a detailed model of an existing installation of a GE PETtrace 16.5 MeV cyclotron was developed using FLUKA. An extensive measurement campaign of the neutron ambient dose equivalent H¹(10) in marked positions around the cyclotron was conducted using a neutron rem-counter probe and CR39 neutron detectors. Data from a previous measurement campaign performed by our group using TLDs were also re-evaluated.The FLUKA model was then validated by comparing the results of high-statistics simulations with experimental data. In 10 out of 12 measurement locations, FLUKA simulations were in agreement within uncertainties with all the three different sets of experimental data; in the remaining 2 positions, the agreement was with 2/3 of the measurements.Our work allows to quantitatively validate our FLUKA simulation setup and confirms that Monte Carlo technique can produce accurate results in the energy range of biomedical cyclotrons.     

Proton range monitoring with in-beam PET: Monte Carlo activity predictions and comparison with cyclotron data

GoalProton treatment monitoring with Positron-Emission-Tomography (PET) is based on comparing measured and Monte Carlo (MC) predicted β⁺ activity distributions. Here we present PET β⁺ activity data and MC predictions both during and after proton irradiation of homogeneous PMMA targets, where protons were extracted from a cyclotron.Methods and materialsPMMA phantoms were irradiated with 62 MeV protons extracted from the CATANA cyclotron. PET activity data were acquired with a 10 × 10 cm² planar PET system and compared with predictions from the FLUKA MC generator. We investigated which isotopes are produced and decay during irradiation, and compared them to the situation after irradiation. For various irradiation conditions we compared one-dimensional activity distributions of MC and data, focussing on Δw50%, i.e., the distance between the 50% rise and 50% fall-off position.ResultsThe PET system is able to acquire data during and after cyclotron irradiation. For PMMA phantoms the difference between the FLUKA MC prediction and our data in Δw50% is less than 1 mm. The ratio of PET activity events during and after irradiation is about 1 in both data and FLUKA, when equal time-frames are considered. Some differences are observed in profile shape.ConclusionWe found a good agreement in Δw50% and in the ratio between beam-on and beam-off activity between the PET data and the FLUKA MC predictions in all irradiation conditions.     

The formation constants of dimethylthallium(III)-glutathione complexes in aqueous solution

The complexes formed in the dimethylthallium(III) (Me₂Tl⁺), glutathionate (EGC³⁻) and hydrogen ion system in aqueous solution at 37 °C and I = 150 mmol dm⁻³ (NaCl) have been characterised by means of glass-electrode potentiometry. Glutathione protonation constants were found to be 9.123 ± 0.007, 17.42 ± 0.01, 20.78 ± 0.02, and 22.93 ± 0.02. Formation constants for the complexes [(Me₂Tl)EGCH]⁻ and [(·Me₂Tl) EGC]²⁻ were found to be 11.19 ± 0.03 and 2.39 ± 0.02, respectively. Particular attention has been paid to the evaluation of the effect of possible systematic errors on the constant values determined. Reliable standard deviation estimations have been made by applying a Monte Carlo calculation technique.     

Study of radon/thoron exhalation rate,soil-gas radon concentration,and assessment of indoor radon/thoron concentration in Siwalik Himalayas of Jammu & Kashmir

In the present study, the soil-gas radon concentration was assessed at different depth intervals, i.e., 15 cm, 30 cm, 60 cm, and 100 cm from the 30 villages of Jammu &; Kashmir, India using RAD7, an electrostatic solid state alpha detector. The radon mass exhalation and thoron surface exhalation rate has also been measured in the selected 18 soil samples out of 30 of different grain sizes (i.e., 1 mm, 300 µm, 150 µm). The active radon and thoron concentrations were also assessed in the 20 villages. Both the exhalation rates and active radon/thoron concentration were measured using SMART Rn Duo, a portable radon monitor. The average values of soil-gas radon concentration were 210 ± 84 Bq m^?3, 1261 ± 963 Bq m^?3, 4210 ± 1994 Bq m^?3, and 671 ± 305 Bq m^?3 at the depth intervals of 15 cm, 30 cm, 60 cm, and 100 cm, respectively. The exhalation rate of radon and thoron from soil was found to decrease with the increase of grain size, as smaller soil particles make relatively more contribution to radon and thoron exhalations from the ground surface than larger soil particles. The measured Pearson's correlation coefficient was obtained as statistically significant between different quantities under two-tailed test.     

Generation and anisotropy of neutron emission from a condensed Z-pinch

The paper presents results of measurements of neutron emission generated in the constriction of a fast Z-pinch at the S-300 facility (2 MA, 100 ns). An increased energy concentration was achieved by using a combined load the central part of which was a microporous deuterated polyethylene neck with a mass density of 100 mg/cm³ and diameter of 1–1.5 mm. The neck was placed between two 5-mm-diameter agar-agar cylinders. The characteristics of neutron emission in two axial and two radial directions were measured by the time-of-flight method. The neutron spectrum was recovered from the measured neutron signals by the Monte Carlo method. In all experiments, the spatiotemporal characteristics of plasma in the Z-pinch constriction were measured by means of the diagnostic complex of the S-300 facility, which includes frame photography in the optical, VUV, and soft X-ray (SXR) spectral regions; optical streak imaging; SXR detection; and time-integrated SXR photography. The formation of hot dense plasma in the Z-pinch constriction was accompanied by the generation of hard X-ray (with photon energies E > 30 keV), SXR (with photon energies E > 1 keV and duration of 2–4 ns), and neutron emission. Anisotropy of the neutron energy distribution in the axial direction was revealed. The mean neutron energies measured in four directions at angles of 0° (above the anode), 90°, 180° (under the cathode), and 270° with respect to the load axis were found to be of 2.1 ± 0.1, 2.5 ± 0.1, 2.6 ± 0.2, and 2.4 ± 0.1 MeV, respectively. For a 1-mm-diameter neck, the maximum integral neutron yield was 6 × 10⁹ neutrons. The anisotropy of neutron emission for a Z-pinch with a power-law distribution of high-energy ions is calculated.     

Spatial distributions and dose assessment of natural radionuclides in rocks and soils of some selected sites in southwestern Nigeria

The activity concentrations of ²³⁸U, ²³²Th, and ⁴⁰K in rock and soil samples collected from Ondo and Ekiti States in southwestern Nigeria were measured by using gamma-ray spectrometer with a high-purity germanium (HPGe) detector. The mean activity concentrations of ²³⁸U, ²³²Th, and ⁴⁰K in the rock were 25.53, 61.12, and 554.20 Bq kg^?1 respectively, while that of the soil were 8.27, 17.37, and 151.72 Bq kg^?1 respectively. Results showed that the activity concentrations of ²³⁸U, ²³²Th, and ⁴⁰K were higher in the rocks than the soils of the areas studied. To assess the radiological impact of some radionuclides on the population in the region, the annual effective dose equivalent (AEDE), annual gonadal equivalent dose (AGED), and excess lifetime cancer risk (ELCR) were calculated. The mean values of the indoor and outdoor AEDE, and AGED were 88.08 µSv y^?1, 352.34 µSv y^?1, and 508.40 mSv y^?1, respectively for the rock samples, and 25.31 µSv y^?1, 101.25 µSv y^?1, and 145.80 mSv y^?1 respectively for the soil samples. The mean values obtained for AEDE and AGED for the soil were below ICRP recommended limits of 1 and 300 mSv y^?1, respectively. AGED for the rocks was higher than the maximum permissible limit.     

Dosimetric response of tooth enamel to 14 Mev neutrons

The electron paramagnetic resonance (EPR) response of tooth enamel in a monenergetic neutron beam of 14 MeV was studied, with the aim to evaluate the relative neutron to ⁶⁰Co sensitivity. Three samples of tooth enamel powder were irradiated in air. A whole tooth and a powdered sample were irradiated in a geometrical PMMA phantom, in order to simulate the real exposure of a tooth inside a human head. The measured dose in enamel was compared to the dose calculated by Monte Carlo simulation. The relative neutron to ⁶⁰Co sensitivity using different reference materials (air, water and enamel) was evaluated as well. Large differences in sensitivity values were found depending on the reference material: the obtained relative neutron to ⁶⁰Co sensitivity was 0.47±0.09 for enamel and 0.15±0.03 for water. A comparison with results in fast neutron fields is reported.     

DS02 fluence spectra for neutrons and gamma rays at Hiroshima and Nagasaki with fluence-to-kerma coefficients and transmission factors for sample measurements

Fluence spectra at several ground distances in Hiroshima and Nagasaki are provided along with associated fluence-to-kerma coefficients from the Dosimetry System 2002 (DS02). Also included are transmission factors for calculating expected responses of in situ sample measurements of neutron activation products such as ³²P,³⁶Cl,³⁹Ar,⁴¹Ca, ⁶⁰Co,⁶³Ni,¹⁵²Eu, and ¹⁵⁴Eu. The free-in-air (FIA) fluences calculated in 2002 are available for 240 angles, 69 energy groups, 101 ground distances, 5 heights, 4 radiation source components, 2 cities. The DS02 code uses these fluences partitioned to a prompt and delayed portion, collapsed to 58 energy groups and restricted to 97 ground distances. This is because the fluence spectra were required to be in the same format that was used in the older Dosimetry System 1986 (DS86) computer code, of which the DS02 computer code is a modification. The 2002 calculation fluences and the collapsed DS02 code fluences are presented and briefly discussed. A report on DS02, which is available on the website at the Radiation Effects Research Foundation, provides tables and figures of the A-bomb neutron and gamma-ray output used as the sources in the 2002 radiation transport calculations. While figures illustrating the fluence spectra at several ground ranges are presented in the DS02 Report, it does not include any tables of the calculated fluence spectra in the DS02 report. This paper provides, at several standard distances from the hypocenter, the numerical information which is required to translate the FIA neutron fluences given in DS02 to a neutron activation measurement or neutron and gamma-ray soft-tissue dose.     

Production of Ga-68 with a General Electric PETtrace cyclotron by liquid target

PurposeIn recent years the use of ⁶⁸Ga (t_1/2 = 67.84 min, β⁺: 88.88%) for the labelling of different PET radiopharmaceuticals has significantly increased. This work aims to evaluate the feasibility of the production of ⁶⁸Ga via the ⁶⁸Zn(p,n)⁶⁸Ga reaction by proton irradiation of an enriched zinc solution, using a biomedical cyclotron, in order to satisfy its increasing demand.MethodsIrradiations of 1.7 M solution of ⁶⁸Zn(NO₃)₂ in 0.2 N HNO₃ were conducted with a GE PETtrace cyclotron using a slightly modified version of the liquid target used for the production of fluorine-18. The proton beam energy was degraded to 12 MeV, in order to minimize the production of ⁶⁷Ga through the ⁶⁸Zn(p,2n)⁶⁷Ga reaction. The product’s activity was measured using a calibrated activity meter and a High Purity Germanium gamma-ray detector.ResultsThe saturation yield of ⁶⁸Ga amounts to (330 ± 20) MBq/µA, corresponding to a produced activity of ⁶⁸Ga at the EOB of (4.3 ± 0.3) GBq in a typical production run at 46 µA for 32 min. The radionuclidic purity of the ⁶⁸Ga in the final product, after the separation, is within the limits of the European Pharmacopoeia (>99.9%) up to 3 h after the EOB. Radiochemical separation up to a yield not lower than 75% was obtained using an automated purification module. The enriched material recovery efficiency resulted higher than 80–90%.ConclusionsIn summary, this approach provides clinically relevant amounts of ⁶⁸Ga by cyclotron irradiation of a liquid target, as a competitive alternative to the current production through the ⁶⁸Ge/⁶⁸Ga generators.     

Radiological toxicity of some fish and meat tissues consumed in southwestern Nigeria

The activity concentrations of natural radionuclides in 30 fish tissues and 30 meat organs have been determined using high purity germanium (HPGe) detector. For the fish tissues, the mean activity concentrations of ²³⁸U and ²³²Th were highest in Catfish (Clarias gariepinus) with values of 5.31 ± 1.30 and 6.09 ± 0.91 Bq/kg, respectively. The lowest mean activity concentrations of ²³⁸U and ²³²Th were seen in Titus (Scomberomorus tritor) and Croaker (Micropogonias undulatus), Croaker with values of 1.51 ± 2.08 and 64.42 ± 6.33 Bq/kg, respectively. The mean activity concentration of ⁴⁰K was highest in Micropogonias undulatus and lowest in Tilapia (Oreohronis niloticus) with values of 64.42 ± 6.33 and 6.53 ± 0.98 Bq/kg. For the meat organs, the highest mean activity concentration of ²³⁸U, ²³²Th, and ⁴⁰K was highest in kidney, liver, and heart, respectively with values of 2.82 ± 0.47, 4.57 ± 0.69, and 52.07 ± 7.81 Bq/kg. Small intestine had the lowest mean activity concentrations of ²³⁸U and ²³²Th with values of 1.14 ± 0.16 and 0.89 ± 0.08 Bq/kg, respectively. Beef had the lowest mean activity concentration of ⁴⁰K with a value of 17.61 ± 2.14 Bq/kg.     

Thoron levels in traditional Chinese residential dwellings

A survey on radon (²²²Rn), thoron (²²⁰Rn) and its decay products (²²⁰RnD) was conducted in Chinese traditional residential dwellings constructed with loam bricks or soil wall. The activity concentrations in 164 dwellings under investigation were 72.4±59.2 (arithmetic mean, AM) and 57.5±2.0 Bq m⁻³ (geometric mean, GM) for ²²²Rn, and 318±368 and 162±3.7 Bq m⁻³ for ²²⁰Rn, respectively. For ²²⁰RnD, 67 dwellings were studied. The AM of the ²²⁰RnD equilibrium equivalent concentration was 3.8±3.3 Bq m⁻³ with a maximum value of 15.8 Bq m⁻³. On the basis of these results, the average annual effective doses to the local residents due to radon and thoron exposure were 1.44–4.62 mSv. Thoron contributes 12.9–56.6% to the total doses. Preliminary results show that there is a relation between ²²⁰RnD in air and ²³²Th in soil. The correlation factors of outdoor and indoor were 0.88 and 0.40. The ²³²Th activity content of Chinese soil is estimated to be about two times the world average. The traditional residential dwellings with soil construction are still common in China. Further investigations on the ²²⁰Rn level in these dwelling with the aim of dose reduction are proposed.     

Radionuclides content in grape molasses soil samples from Central Black Sea region of Turkey

The activity concentrations of radionuclides in grape molasses soil samples collected from Zile (Tokat) plain in the Central Black Sea region of Turkey were measured by using gamma spectrometer with a NaI(Tl) detector. Also, the concentrations of ²²²Rn in soil samples and air were estimated essentially taking the activity concentrations of ²²⁶Ra measured in soil samples. Grape molasses soil samples with calcium carbonate content are used for sedimentation for making molasses in this region. The average activity concentrations of ²³²Th, ²²⁶Ra, ⁴⁰K, and ¹³⁷Cs were found as 62 ± 2, 68 ± 3, 479 ± 35, and 8.0 ± 0.3 Bq kg^?1, respectively. The average concentrations of ²²²Rn in soil samples and air were estimated to be 50 kBq m^?3 and 144 Bq m^?3. From the activity concentrations, absorbed gamma dose rate in outdoor air (D), annual effective dose from external exposure (E_E), annual effective dose from inhalation of radon (E_I), and excess lifetime cancer risk (ELCR) were estimated in order to assess radiological risks. The average values of D, E_E, E_I, and ELCR were found to be 90 nGy h^?1, 110 μSv y^?1, 1360 μSv y^?1, and 4 × 10^?4, respectively.     

Blood clearance and occupational exposure for <Superscript>177</Superscript>Lu-DOTATATE compared to <Superscript>177</Superscript>Lu-PSMA radionuclide therapy

The main target of this work is to examine blood clearance and external exposure for ¹⁷⁷Lu-DOTATATE compared with new emerging ¹⁷⁷Lu-PSMA therapy. Blood clearance and radiation exposure of 31 patients treated with 5.5?±?1.1 GBq ¹⁷⁷Lu-DOTATATE were compared to those of 23 patients treated with 7.4 GBq ¹⁷⁷Lu-PSMA. Dose rates were measured at several distances and time points up to 120 h after treatment. Blood samples were collected conjunctively after infusion. Caregiver’s cumulative dose was measured by means of an OSL (optically stimulated luminescence) dosimeter for 4–5 days and medical staff’s dose was also estimated using electronic personal dosimeters. Finger dose was determined via ring TLD (Thermoluminescence Dosimeter) for radiopharmacists and nurses. Dose rates due to ¹⁷⁷Lu-DOTATATE at a distance of 1 m, 4 h and 6 h after infusion, were 3.0?±?2.8 and 2?±?1.9 µSv/(h GBq), respectively, while those due to ¹⁷⁷Lu-PSMA were 3.1?±?0.8 and 2.2?±?0.9 µSv/(h GBq). Total effective dose of 17 caregivers was 100–200 µSv for ¹⁷⁷Lu-DOTATATE therapy. Mean effective doses to nurses and radiopharmacists were 5 and 4 µSv per patient, respectively, while those for physicists and physicians were 2 µSv per patient. For ¹⁷⁷Lu-DOTATATE, effective half-life in blood and early elimination phase were 0.31?±?0.13 and 4.5?±?1 h, while they were found as 0.4?±?0.1 and 5?±?1 h, respectively, for ¹⁷⁷Lu-PSMA. The first micturition time following ¹⁷⁷Lu-DOTATATE infusion was noted after 36?±?14 min, while the second and third voiding times were after 74?±?9 and 128?±?41 min, respectively. It is concluded that blood clearance and radiation exposure for ¹⁷⁷Lu-DOTATATE are very similar to those for ¹⁷⁷Lu-PSMA, and both treatment modalities are reasonably reliable for outpatient treatment, since the mean dose rate [2.1 µSv/(h GBq)] decreased below the dose rate that allows release of the patient from the hospital (20 µSv/h) after 6 h at 1 m distance.     

Probability Density Functions Describing 24-Hour Inhalation Rates For Use in Human Health Risk Assessments

A Monte Carlo simulation was undertaken to estimate the amount of air inhaled over a typical 24-hour period by six age groups of Canadians. The objective of the simulation was to derive probability density functions that could be used to describe inhalation rates in probabilistic health risk assessments involving airborne contaminants. The six age groups considered were those typically employed in human health risk assessments in Canada: infants (aged 0 to 6 months), toddlers (aged 7 months to 4 years), children (aged 5 to 11 years), teenagers (aged 12 to 19 years), adults (aged 20 to 59 years), and seniors (aged 60 years and older). The resulting distributions are considered equally applicable to Americans as Canadians, however, since the study relied heavily on time-activity information gathered in the USA. Existing time-activity and breathing rate studies were reviewed in order to define random variables describing probable durations that North Americans spend at various levels of activity and their probable inhalation rates while at each level of activity. These random variables were combined in a Monte Carlo simulation to empirically generate probability density functions describing 24-hour inhalation rates for each age group. The simulation suggested that most age groups' 24 hour inhalation rates can be represented with log-normal probability density functions. Arithmetic mean values and standard deviations for these distributions are as follows: approximately 9.3 ± 2.4?m³/day for toddlers; 14.6 ± 3.0?m³/day for children; 15.8 ± 3.7?m³/day for teenagers; 16.2 ± 3.8?m³/day for adults; and 14.2 ± 3.3?m³/day for seniors. The distribution of infants' 24-hour inhalation rates was found to be better represented by a normal distribution than a log-normal distribution. The mean and standard deviation for the infants' normal distribution are 2.1 ± 0.58?m³/day. Inhalation rates were also estimated separately for male and female toddlers, children, teenagers, adults and seniors. These estimates suggested that males inhale on average 8% to 27% more air than females of the same age. Because infants' activity patterns and minute volumes did not appear to be strongly correlated with gender, a single probability density function was deemed satisfactory to describe male and female infants' 24-hour inhalation rates.     

Risk assessment of natural radioactivity in surface water and sediments from a waterfall site in Osun State,Nigeria

Activity concentration of natural radionuclides in surface water and sediment from a waterfall site, Erin-Oke, Osun, Nigeria, has been determined by gamma spectrometry. The mean activity concentration of ⁴⁰K, ²²⁶Ra, and ²³²Th were estimated to be 61.015 ± 15.50, 8.165 ± 2.05 and 5.24 ± 1.57 Bq/l, respectively in water samples and 172.023 ± 35.433, 19.282 ± 4.95, and 17.089 ± 4.37 Bq/kg respectively in sediment samples. Total annual effective dose ingested by an individual ranges from 10.73 ± 3.36 to 15.18 ± 4.44 mSv/y, 2.50 ± 0.80 to 3.58 ± 0.96 mSv/y, and 2.30 ± 0.72 to 3.23 ± 0.93 mSv/y, with mean values of 13.25 ± 3.89, 3.10 ± 0.90, and 2.83 ± 0.83 mSv/y for infants, children, and adults, respectively. These values are greater than International Commission on Radiological Protection (ICRP) and the World Health Organization's recommended limit of 1.0 and 0.1 msv/y, respectively. Mean activity concentrations in sediment are 172.023 ± 35.433, 19.823 ± 4.95, and 17.089 ± 4.37 Bq/kg for ⁴⁰K, ²²⁶Ra, and ²³²Th, respectively, with mean absorbed dose of 26.91 nGyh^?1. This value is lesser than UNSCEAR world average value of 55 nGyh^?1. Health hazard index and radium equivalent for sediments showed lower values than absorbable limits.     

Multi-targeted dihydrazones as potent biotherapeutics

Hydrazone compounds were considered as a useful moiety in drug design development. Therefore, these studies were aimed at the synthesis of new dihydrazones and were screened for their in vitro H⁺/K⁺-ATPase and anti-inflammatory activities. The results revealed that compounds 9 (22 ± 0.62 µg/mL), 10 (26 ± 0.91 µg/mL), 15 (24 ± 0.44 µg/mL), 16 (28 ± 0.63 µg/mL), 17 (12 ± 0.38 µg/mL), 18 (14 ± 0.47 µg/mL), 19 (26 ± 0.54 µg/mL), 20 (16 ± 0.41 µg/mL), 25 (06 ± 0.68 µg/mL) and 26 (08 ± 0.43 µg/mL) showed excellent H⁺/K⁺-ATPase activity and their IC₅₀ value were lower than the standard drug Omerazole (48 ± 0.12 µg/mL). Compounds 5 (28 ± 0.65 µg/mL), 6 (24 ± 0.61 µg/mL), 7 (28 ± 0.64 µg/mL), 8 (26 ± 0.45 µg/mL), 11 (30 ± 0.74 µg/mL), 12 (28 ± 0.40 µg/mL), 13 (32 ± 0.24 µg/mL), 14 (30 ± 0.55 µg/mL) and 21 (08 ± 0.47 µg/mL), 22 (12 ± 0.47 µg/mL), 23 (10 ± 0.51 µg/mL) and 24 (14 ± 0.84 µg/mL) showed better anti-inflammatory activity compared to standard indomethacin (44 ± 0.15 µg/mL). The structure activity relationship (SAR) showed that, electron donating groups (OH, OCH₃) favored the H⁺/K⁺-ATPase and antioxidants activity, whereas, electron withdrawing groups (F, Cl, Br and NO₂) favored the anti-inflammatory activity. Furthermore, molecular docking study was performed to investigate the binding interactions of the most active analogs with the active site of H⁺/K⁺-ATPase enzyme. Compounds 25 (G-score = −9.063) and 26 (G-score = −8.977) showed the highest docking G-scores for H⁺/K⁺-ATPase inhibition activity.     

Size-fractionated chlorophyll a and primary productivity in the Chukchi Sea and its northern Chukchi Plateau

Investigations on chlorophyll a and primary productivity were carried out in the Chukchi Sea and its northern Chukchi Plateau during the 2^nd Chinese National Arctic Research Expedition in the summer of 2003. The results showed that chlorophyll a concentrations were 0.009–30.390 μg/dm³ at the surveyed waters; the surface chlorophyll a concentrations were 0.050–4.644 μg/dm³ and the average value was (0.875±0.981) μg/dm³ in the surveyed area. In the Chukchi Sea Shelf, chlorophyll a concentrations at the depth from 10 m to bottom were higher than that in the surface water, and the concentrations were lower at the depth below 75 m in the Chukchi Plateau. Chlorophyll a concentrations descended in 3 sequential samplings on Transect R, with average values of (2.564±1.496) μg/dm³, (1.329±0.882) μg/dm³ and (0.965±0.623) μg/dm³, respectively. The potential primary productivity ((2.305± 1.493) mgC/(m³·h)) in the Chukchi Sea was higher than that ((0.527±0.374) mgC/(m³·h)) in the Chukchi Plateau. The results of the size-fractionated chlorophyll a and primary productivity showed that microplankton accounted for the majority of the total chlorophyll a (63.13%) and primary productivity (65.16%) at the survey stations. The contributions of the nanoplankton and picoplankton to the total chlorophyll a and primary productivity were roughly the same.     

In vitro flowering red miniature rose

Using aseptic plantlets obtained from stem node explants of hybrid red miniature rose (Rosa hybrida cv. Fairy Dance), the effects of shoot physiological status, medium ingredients, and culture thermoperiod on in vitro flowering were evaluated. Shoot height, subculture media for shoot multiplication, sucrose concentration, plant growth regulators (PGRs), mineral substances in media, and thermoperiod had a significant effect on the percentage of in vitro flowering. Shoots 3 ± 0.2 or 2 ± 0.2 cm in height cultured on Murashige and Skoog (MS) medium containing 2.0 mg dm^?3 6-benzyladenine (BA), 0.2 mg dm^?3 α-naphthaleneacetic acid (NAA), and 20 g dm^?3 sucrose were more suitable for in vitro flowering than shoots 4 ± 0.2, or 5 ± 0.2 cm in height. The most suitable sucrose concentration for in vitro flowering was 50 g dm^?3 and the most suitable PGRs were a combination of 3.0 mg dm^?3 BA and 0.1 mg dm^?3 NAA. Increasing the potassium nitrate to ammonium nitrate ratio or increasing the phosphate concentration in MS medium had a positive effect on in vitro flowering. The percentage of in vitro flowering was significantly higher at day/night temperature of 28/20 °C than at other constant temperatures. The percentage of in vitro flowering shoots reached 68.33 % despite the occurrence of abnormal flowers and some unique developmental patterns. It makes miniature rose a potentially new in vitro experimental platform for research on the molecular mechanisms of flowering ornamental plants.     

Measurements of radon activity concentration in mouse tissues and organs

The purpose of this study is to investigate the biokinetics of inhaled radon, radon activity concentrations in mouse tissues and organs were determined after mice had been exposed to about 1 MBq/m³ of radon in air. Radon activity concentrations in mouse blood and in other tissues and organs were measured with a liquid scintillation counter and with a well-type HP Ge detector, respectively. Radon activity concentration in mouse blood was 0.410?±?0.016 Bq/g when saturated with 1 MBq/m³ of radon activity concentration in air. In addition, average partition coefficients obtained were 0.74?±?0.19 for liver, 0.46?±?0.13 for muscle, 9.09?±?0.49 for adipose tissue, and 0.22?±?0.04 for other organs. With these results, a value of 0.414 for the blood-to-air partition coefficient was calculated by means of our physiologically based pharmacokinetic model. The time variation of radon activity concentration in mouse blood during exposure to radon was also calculated. All results are compared in detail with those found in the literature.     

Calculation of the 3-D dose distribution surrounding a 103Pd stent

Purpose: This study was designed to assess the suitability of a ¹⁰³Pd-implanted stent for use in intravascular brachytherapy. Materials and methods: A stent was modeled as a superposition of 201 identical struts and the EGS4/DOSRZ Monte Carlo code was used to calculate the dose distribution for each strut. To verify the simulation parameters, doses along the transverse axis of a Model 200 ¹⁰³Pd interstitial seed were calculated and compared to those calculated by the TG43 method. Results: Dose profiles within 1 mm of the stent's outer surface were heterogeneous and reflected the stent's structure. For a 2-mm outer-diameter ¹⁰³Pd-implanted stent, ∼2.68×10⁷ Bq were required to deliver 31.5 Gy in 28 days at a distance of 0.5 mm along the perpendicular bisector from the stent's outer surface. The Monte Carlo simulation of the ¹⁰³Pd seed showed relative doses within 7% of the values calculated by the TG43 method. Conclusion: The dosimetry about a ¹⁰³Pd-implanted stent suggests that the stent is suitable for use in intravascular brachytherapy.